HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
HNF­
2600,
Revision
15
May
11,
2005
HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
HNF­
2600
Revision
15
Approved
by:
Signature
on
file
Date:
05/
11/
2005
Office
Director,
CBFO
Office
of
Characterization
and
Transportation
(
print/
sign)

Approved
by:
Signature
on
file
Date:
05/
11/
2005
Manager,
CBFO
Quality
Assurance
(
print/
sign)

Approved
by:
Signature
on
file
Date:
05/
10/
2005
Site
Project
Manager
(
print/
sign)

Approved
by:
Signature
on
file
Date:
05/
10/
2005
Site
Quality
Assurance
Officer
(
print/
sign)

Approved
by:
Signature
on
file
Date:
05/
10/
2005
Waste
Certification
Official
(
print/
sign)

Approved
by:
Signature
on
file
Date:
05/
10/
2005
Transportation
Certification
Official
(
print/
sign)

Approved
by:
Signature
on
file
Date:
05/
10/
2005
RL
Project
Director
(
print/
sign)
HNF­
2600,
REV
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5/
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2005
HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
TABLE
OF
CONTENTS
1.0
INTRODUCTION
..............................................................................................................
16
2.0
CERTIFICATION
PROJECT
ORGANIZATION
AT
THE
HANFORD
SITE
................
19
2.1
ORGANIZATION
AND
RESPONSIBILITIES..........................................................
19
2.2
WASTE
CHARACTERIZATION/
CERTIFICATION
PROCESS.............................
25
2.3
CERTIFICATION
PROJECT
DOCUMENT
CONTROL
AND
RECORDS
MANAGEMENT.....................................................................................................................
41
3.0
COMPLIANCE
PLAN
FOR
CH­
WAC.............................................................................
42
3.1
SUMMARY
OF
WIPP
AUTHORIZATION
BASIS
..................................................
42
3.2
CONTAINER
PROPERTIES
CRITERIA
AND
REQUIREMENTS
.........................
47
3.3
RADIOLOGICAL
PROPERTIES
CRITERIA
AND
REQUIREMENTS..................
53
3.4
PHYSICAL
PROPERTIES
CRITERIA
AND
REQUIREMENTS.............................
61
3.5
CHEMICAL
PROPERTIES
CRITERIA
AND
REQUIREMENTS
...........................
61
3.6
DATA
PACKAGES
CONTENTS...............................................................................
64
4.0
HANFORD
COMPLIANCE
PLAN
FOR
CH­
TRAMPAC...............................................
66
4.1
CH­
TRUCON
Document.............................................................................................
67
4.2
Compliance
Program....................................................................................................
70
4.3
CONTAINER
AND
PHYSICAL
PROPERTIES
REQUIREMENTS........................
71
4.4
NUCLEAR
PROPERTIES
REQUIREMENTS...........................................................
80
4.5
CHEMICAL
PROPERTIES
REQUIREMENTS.........................................................
89
4.6
GAS
GENERATION
REQUIREMENTS
...................................................................
99
4.7
PAYLOAD
ASSEMBLY
REQUIREMENTS...........................................................
175
5.0
QUALITY
ASSURANCE
PLAN
....................................................................................
188
5.1
ORGANIZATION
AND
QA
PROGRAM
................................................................
191
5.2
PERSONNEL
QUALIFICATION
AND
TRAINING...............................................
193
5.3
QUALITY
IMPROVEMENT....................................................................................
194
5.4
DOCUMENTS...........................................................................................................
195
5.5
RECORDS
.................................................................................................................
195
5.6
WORK
PROCESSES.................................................................................................
196
5.7
PROCUREMENT......................................................................................................
197
5.8
INSPECTION
AND
TESTING
.................................................................................
198
5.9
ASSESSMENT
REQUIREMENTS
..........................................................................
200
5.10
SAMPLE
CONTROL
REQUIREMENTS
................................................................
202
5.11
SCIENTIFIC
INVESTIGATION
REQUIREMENTS...............................................
202
5.12
SOFTWARE
REQUIREMENTS
..............................................................................
203
6.0
REFERENCES
.................................................................................................................
203
HNF­
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2005
HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
ACRONYMS
AND
ABBREVIATIONS
AK
acceptable
knowledge
ASME
American
Society
of
Mechanical
Engineers
ASTM
American
Society
for
Testing
and
Materials
C
of
C
Certificate
of
Compliance
CAR
corrective
action
report
CBFO
Carlsbad
Field
Office
Certification
Plan
Hanford
Site
Transuranic
Waste
Certification
Plan.
CFR
Code
of
Federal
Regulations
CH
contact­
handled
CH­
DSA
Contact­
handled
Documented
Safety
Analysis
CH­
TRAMPAC
Contact
Handled
Transuranic
Waste
Authorized
Methods
for
Payload
Control
CH­
TRUCON
Contact­
Handled
Transuranic
Waste
Content
Codes
(
document)
CH
TRU
contact­
handled
transuranic
CH­
WAC
Contact­
Handled
Transuranic
Waste
Acceptance
Criteria
for
the
Waste
Isolation
Pilot
Plant
CIN
container
identification
number
CPR
cellulosics/
plastic
&
rubber
CWC
Central
Waste
Complex
DOE
U.
S.
Department
of
Energy
DOE­
RL
U.
S.
Department
of
Energy­
Richland
Operations
Office
DOT
U.
S.
Department
of
Transportation
dpm
disintegration(
s)
per
minute
DQO
data
quality
objective
EPA
U.
S.
Environmental
Protection
Agency
FH
Fluor
Hanford
FGE
fissile
gram
equivalent
FGE/
g
mass
values
by
239Pu
FGE
conversion
factors
ICV
inner
containment
vessel
LDR
land
disposal
restriction
LWA
Land
Withdrawal
Act
M&
O
management
and
operating
mrem/
hr
milliroentgen(
s)
equivalent
man
per
hour
MS
mass
spectrometry
NIST
National
Institute
of
Standards
and
Technology
nCi/
g
nanocurie(
s)
per
gram
NCR
nonconformance
report
HNF­
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HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
NDA
nondestructive
assay
NDE
nondestructive
examination
NFT
Nuclear
Filter
Technology
NMED
New
Mexico
Environment
Department
NRC
U.
S.
Nuclear
Regulatory
Commission
OCA
outer
containment
assembly
OCV
outer
containment
vessel
OPCTCD
Overpack
Payload
Container
Transportation
Certification
Document
PATCD
Payload
Assembly
Transportation
Certification
Document
PCB
polychlorinated
biphenyl
PCTCD
Payload
Container
Transportation
Certification
Document
PDP
performance
demonstration
program
PE­
Ci
plutonium­
239
(
239Pu)
equivalent­
curie(
s)
PFP
Plutonium
Finishing
Plant
Project
Hanford
Site
Transuranic
Waste
Certification
Project
QA
quality
assurance
QAO
quality
assurance
objective
QAPD
DOE/
CBFO
Quality
Assurance
Program
Document
QAPD
Procedures
Matrix
Hanford
Site
TRU
Waste
Project
Quality
Assurance
Program
Document
Procedures
Matrix
QAPjP
Hanford
Site
Transuranic
Waste
Characterization
Quality
Assurance
Project
Plan
QC
quality
control
RCRA
Resource
Conservation
and
Recovery
Act
RCT
radiological
control
technician
RH
remote­
handled
RMS
root­
mean­
square
RSS
root­
sum­
of­
squares
RTR
real­
time
radiography
SAR
safety
analysis
report
SPM
site
project
manager
SQAO
site
quality
assurance
officer
SVOC
semivolatile
organic
compound
SW­
846
Test
Methods
for
Evaluating
Solid
Waste,
Physical/
Chemical
Methods
SWB
standard
waste
box
SWD
Solid
Waste
Disposal
TC
toxicity
characteristic
TCO
transportation
certification
official
TDOP
ten­
drum
overpack
HNF­
2600,
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2005
HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
TIC
tentatively
identified
compound
TRU
transuranic
TRUPACT­
II
Transuranic
Package
Transporter­
II
TRUPACT­
II
SARP
Safety
Analysis
Report
for
the
TRUPACT­
II
Shipping
Package
TWBIR
Transuranic
Waste
Baseline
Inventory
Report
VOC
volatile
organic
compound
WAP
Waste
Analysis
Plan
(
Attachment
B
of
WIPP
Hazardous
Waste
Facility
Permit)
WCO
waste
certification
official
WIPP
Waste
Isolation
Pilot
Plant
WRAP
Waste
Receiving
and
Processing
WSPF
Waste
Stream
Profile
Form
WWIS
Waste
Isolation
Pilot
Plant
Waste
Information
System
HNF­
2600,
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2005
HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
DEFINITIONS
Acceptable
knowledge
(
AK)
­
An
EPA
term,
which
includes
process
knowledge
and
results
from
previous
testing,
sampling,
and
analysis,
associated
with
the
waste.
AK
includes
information
regarding
the
raw
materials
used
in
a
process
or
operation,
process
description,
products
produced,
and
associated
wastes.
AK
documentation
includes
the
site
history
and
mission,
site­
specific
processes
or
operations,
administrative
building
controls,
and
all
previous
and
current
activities
that
generate
a
specific
waste.

Activity
 
A
measure
of
the
rate
at
which
a
material
emits
nuclear
radiation,
usually
given
in
terms
of
the
number
of
nuclear
disintegrations
occurring
in
a
given
length
of
time.
The
common
unit
of
activity
is
the
curie,
which
amounts
to
37
billion
(
3.7
x
1010)
disintegrations
per
second.
The
International
Standard
unit
of
activity
is
the
Becquerel
and
is
equal
to
one
disintegration
per
second.

Aluminum
honeycomb
spacer
assembly
­
An
assembly
that
is
located
within
each
end
of
the
inner
containment
vessel
(
ICV)
to
provide:

1.
A
generous
void
volume
to
accommodate
payload
gas
generation.

2.
An
energy­
absorbing
barrier
between
the
payload
and
the
ICV
dished
heads.

Assay
­
The
observation
of
spontaneous
or
stimulated
nuclear
radiations,
interpreted
to
estimate
the
content
of
one
or
more
radionuclides
in
a
material.

Assessment
­
Evaluation
process
used
to
measure
the
performance
or
effectiveness
of
a
system
and
its
elements.
Assessment
is
an
all­
inclusive
term
used
to
denote
any
of
the
following:
audit,
performance
evaluation,
management
systems
review,
peer
review,
inspection,
or
surveillance.

Atomic
energy
defense
activities
 
Activities
of
the
Secretary
of
Energy
(
and
predecessor
agencies)
performed
in
whole
or
in
part
in
carrying
out
any
of
the
following
functions:
naval
reactors
development;
weapons
activities,
including
defense
inertial
confinement
fusion;
verification
and
control
technology;
defense
nuclear
material
production;
defense
nuclear
waste
and
materials
byproduct
management;
defense
nuclear
materials
security
investigations;
and
defense
research
and
development.

Audit
­
Planned
and
documented
independent
assessment
to
determine
by
investigation,
examination,
or
evaluation
of
objective
evidence,
the
adequacy
of
and
compliance
with
established
procedures,
instructions,
drawings,
and
other
applicable
documents,
and
the
effectiveness
of
implementation.
An
audit
should
not
be
confused
with
surveillance
or
inspection
activities
performed
for
the
sole
purpose
of
process
control
or
product
acceptance.

Carbon
composite
filter
­
See
filter
vent.

Certification
authority
­
Authorization
to
certify
TRU
waste
to
the
WIPP
waste
acceptance
criteria
(
WAC)
that
is
granted
by
the
permittee
to
those
TRU
waste
generator/
storage
sites
whose
TRU
waste
programs
have
been
evaluated
and
found
to
be
acceptable.
HNF­
2600,
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8
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2005
HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
Certified
waste
­
Payload
containers
loaded
with
waste
that
has
been
verified
to
meet
the
criteria
of
the
CH­
WAC.

Chemical
compatibility
­
Assessing
the
properties
of
all
potential
chemicals
(>
1
weight
percent)
in
a
payload
container.
There
must
be
no
adverse
safety
or
health
hazards
produced
as
a
result
of
any
mixtures
that
could
occur.

Combustible
materials
­
Organic
materials
that
are
dominantly
cellulosic
(
e.
g.,
cotton,
paper,
cloth,
wood,
etc.),
including
plastics.

Compressed
gas
­
Compressed
gases
are
those
materials
defined
as
such
by
49
Code
of
Federal
Regulations
(
CFR)
173,
Subpart
D.

Contact­
handled
TRU
waste
­
Transuranic
waste
packages
that
have
a
surface
dose
rate
not
greater
than
200
mrem/
hr.

Contact­
handled
transuranic
waste
authorized
methods
for
payload
control
(
CH­
TRAMPAC)
 
The
governing
document
for
shipments
in
the
TRUPAC­
II
packagings.

Contact­
handled
transuranic
waste
content
codes
(
CH­
TRUCON)
 
The
document
containing
a
description
of
the
waste
stream,
waste
form,
and
package
configuration
for
each
waste
content
code
authorized
for
shipment
in
the
TRUPACT­
II
packagings.

Content
code
­
A
uniform
system
applied
to
waste
forms
to
group
those
with
similar
characteristics
for
purposes
of
shipment
in
TRUPACT­
II
packagings.

Corrosive
materials
­
Corrosive
materials
are
those
defined
as
such
by
40
CFR
261.22
(
a)(
l).

Curie
 
A
unit
of
activity
equal
to
37
billion
(
3.7
x
1010)
disintegrations
per
second.

Decay
heat
­
Heat
produced
by
radioactive
emissions
that
are
absorbed
in
the
surrounding
material.

Defense
TRU
waste
­
Nuclear
waste
derived
from
the
manufacture
of
nuclear
weapons
and
operation
of
naval
reactors.
Associated
activities
include
(
a)
naval
reactors
development,
(
b)
weapons
activities,
including
defense
inertial
confinement
fusion,
(
c)
verification
and
control
technology,
(
d)
defense
nuclear
materials
production,
(
e)
defense
nuclear
waste
materials
and
byproducts
management,
(
f)
nuclear
waste
and
materials
security
and
investigations,
and
(
g)
research
and
development.
See
permittee
Interim
Guidance
on
Ensuring
Waste
Qualifies
for
Disposal
at
the
Waste
Isolation
Pilot
Plant.

DOE
field
element
­
The
first­
line
DOE
field
element
that
carries
the
organizational
responsibility
for
(
1)
managing
and
executing
assigned
projects,
(
2)
directing
contractors
who
conduct
the
projects,
and
(
3)
ensuring
that
environment,
safety,
and
health
are
integral
parts
of
each
project.
HNF­
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HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
Dose
equivalent
rate
 
The
radiation
dose
equivalent
delivered
per
unit
time
(
e.
g.,
rem
per
hour).

Explosive
materials
­
Explosive
materials
are
those
defined
as
such
by
49
CFR
173,
Subpart
C.

Filter
vent
­
A
filter
vent
is
defined
as
filter
media
manufactured
of
carbon
composite,
Kevlar,
stainless
steel,
or
any
material
that
enables
the
filter
to
meet
the
minimum
performance
specifications
stipulated
in
the
CH­
TRAMPAC.

Fissile
gram
equivalent
(
FGE)
­
The
mass
of
a
fissile
radionuclide
normalized
to
239Pu.

Flammable
volatile
organic
compound
(
VOC)
­
A
headspace
gas
VOC
that
has
a
National
Fire
Protection
Association
(
NFPA)
flammability
hazard
degree
of
3
or
4
and
a
flash
point
of
less
than
100
°
F
or
considered
by
EPA
to
be
a
significant
fire
hazard
under
WIPP
repository
conditions.
Flammable
headspace
gas
VOCs
that
are
evaluated
for
the
TRU
waste
project
are
listed
in
table
5.2­
2
of
the
CH­
TRAMPAC.

G
value
­
The
number
of
molecules
of
gas
species
produced
per
100
electron
volts
of
decay
energy
absorbed
by
the
waste.

Germanium
counter
­
An
assay
system
that
uses
high­
purity
germanium
(
HPGe)
detectors
for
measuring
gamma
radiation.

Glovebox
­
A
sealed
box
with
windows
and
rubber
gloves
attached
to
ports
such
that
an
operator
may
work
inside
the
box
without
risk
of
contamination.

Headspace
 
The
total
contained
volume
of
a
container
minus
the
volume
occupied
by
the
waste
material.

Headspace­
gas
 
The
gas
within
the
headspace
of
a
container.

Immobilized
materials
­
Materials
that
are
fixed
in
a
solidified
matrix
(
e.
g.,
glass,
ceramic,
cement,
concrete).

Inner
containment
vessel
(
ICV)
­
The
assembly
(
comprised
of
a
lid
and
body)
providing
a
secondary
level
of
containment
for
the
payload.
Within
each
end
of
the
ICV
is
an
aluminum
honeycomb
spacer
assembly.

Lower
Limit
of
Detection
 
The
level
of
radioactivity
which,
if
present,
will
yield
a
measured
value
greater
than
the
critical
limit
with
a
95%
probability.
The
critical
limit
is
defined
as
that
value
which
measurements
of
the
background
will
exceed
with
a
5%
probability.

Machine­
compacted
Waste
 
Waste
whose
volume
has
been
reduced
using
a
mechanical
process.

NaI
(
TI)
drum
counter
­
An
assay
system
that
uses
sodium
iodide
scintillation
detectors
for
measuring
gamma
radiation.
HNF­
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2005
HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
Newly
generated
TRU
waste
­
Waste
generated
after
the
development,
approval,
and
implementation
of
a
TRU
waste
characterization
program
that
has
been
granted
certification
authority
by
the
permittee.
Newly
generated
TRU
waste
also
includes
any
previously
generated
waste
(
see
also
retrievably
stored
waste)
that
undergoes
any
form
of
treatment,
processing,
or
repackaging
in
accordance
with
an
approved
quality
assurance
project
plan.

Nondestructive
assay
(
NDA)
­
Assay
methods
for
waste
items
that
do
not
affect
the
physical
or
chemical
form
of
the
material.

Nondestructive
examination
(
NDE)
­
Methods
that
allow
examination
of
the
contents
of
payload
containers
without
affecting
the
chemical
or
physical
forms
of
these
items.
See
also
radiography.

Oil­
Dri
­
A
trade
name
for
a
basically
clay
material
absorbent.

Operational
day
(
also
"
when
in
operation")
­
A
24­
hour
period
in
which
an
NDA
characterization
system
is
to
be
used
to
perform
measurements
for
TRU
wastes.

Operational
week
­
Seven
consecutive
days,
starting
at
7
a.
m.
on
Monday,
in
which
an
NDA
characterization
system
performed
WIPP­
related
measurements
on
one
or
more
days
in
that
week.

Outer
containment
assembly
­
The
assembly
(
comprised
of
a
lid
and
body)
providing
a
primary
level
of
containment
for
the
payload.
The
outer
containment
assembly
(
OCA)
completely
surrounds
the
inner
containment
vessel
and
consists
of
an
exterior
stainless
steel
shell,
a
relatively
thick
layer
of
polyurethane
foam,
and
an
inner
stainless
steel
boundary,
which
forms
the
outer
containment
vessel
(
OCV).

Outer
containment
vessel
­
The
innermost
boundary
of
the
OCA.

Overpack
­
A
container
around
another
container.

Package
­
(
1)
A
packaging
plus
its
contents.
(
2)
The
reusable
Type
B
shipping
container
(
i.
e.,
TRUPACT­
II)
loaded
with
TRU
waste
payload
containers,
which
has
been
prepared
for
shipment
in
accordance
with
the
package
QA
program.
(
3)
In
the
regulations
governing
the
transportation
of
radioactive
materials,
the
packaging
together
with
its
radioactive
contents,
as
presented
for
transport.

Packaging
quality
assurance
plan
­
A
site­
specific
document
that
defines
the
quality
assurance
(
QA)
and
quality
control
(
QC)
activities
applicable
to
usage
of
the
NRC­
approved
packaging.
This
plan
shall
meet
the
requirements
of
10
CFR
Part
71,
Subpart
H.
(
The
Hanford
Site
Packaging
QA
Plan
is
addressed
in
section
5.0
of
the
Certification
Plan.).

Packaging
­
The
packaging
is
the
container
the
waste
is
placed
into
for
shipment
that
meets
the
requirements
of
49
CFR
173,
Subpart
I,
and
10
CFR
71.4.
For
TRU
waste,
the
packaging
is
the
reusable
Type
B
shipping
container
for
transport
of
TRU
waste
payload
containers
(
e.
g.,
TRUPACT­
II).
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Passive­
active
neutron
counter
­
An
assay
system
that
uses
passive
neutron
coincidence
counting
(
PNCC)
to
measure
neutrons
that
occur
spontaneously
(
passive)
and
the
differential
die­
away
technique
(
DDT)
to
measure
those
that
are
induced
as
a
result
of
neutron
interrogation
of
fissile
material
(
active).

Payload
­
CH
TRU
waste
contained
within
one
of
the
approved
configurations
for
shipment
in
the
TRUPACT­
II
(
e.
g.,
fourteen
55­
gallon
drums,
two
SWBs,
etc.).
The
payload
is
considered
to
include
a
lift
pallet
if
SWBs
are
not
used.
Any
dunnage
used
external
to
the
55­
gallon
drums
or
SWBs
is
also
considered
to
be
part
of
the
payload.

Payload
container
­
The
outermost
container
(
e.
g.,
55­
gallon
drum,
standard
waste
box
[
SWB]
or
ten
drum
overpack
(
TDOP)
for
TRU
waste
material
that
is
placed
in
a
reusable
Type
B
shipping
container
(
e.
g.,
TRUPACT­
II
or
RH­
TRU
72­
B
cask)
for
transport.

Payload
assembly
­
An
assembly
of
payload
containers
qualified
for
transport
in
a
TRUPACT­
II.

Payload
pallet
­
A
lightweight
pallet
with
an
aluminum
honeycomb
core
used
for
loading
and
unloading
fourteen
55­
gallon
drums
of
CH
TRU
waste
at
one
time.

Pipe
component
­
A
stainless
steel
container
used
for
packaging
specific
waste
forms
within
a
55­
gallon
drum.
The
pipe
component
is
exclusively
used
as
part
of
the
pipe
overpack.

Pipe
overpack
­
A
payload
container
consisting
of
a
pipe
component
positioned
by
dunnage
within
a
55­
gallon
drum
with
a
rigid,
polyethylene
liner
and
lid.
Fourteen
pipe
overpacks
will
fit
within
the
TRUPACT­
II
packaging.
The
design
and
use
of
a
pipe
overpack
is
controlled
by
the
NRC
issued
Certificate
of
Compliance
when
used
in
the
TRUPACT.

Plutonium
equivalent
curie
(
PE­
Ci)
­
An
equivalent
radiotoxic
hazard
of
a
radionuclide
normalized
to
239Pu.

polyethylene
liners
­
Rigid
drum
liners
molded
from
high­
density
polyethylene,
typically
with
a
wall
thickness
of
about
0.09
inches
(
90
mils).
The
liner
generally
has
a
snap­
on
cover
of
the
same
material.

Pressurized
containers.
Smaller
containers
within
the
payload
container
which
may
hold
compressed
gas.

239Pu
fissile
gram
equivalent
­
See
fissile
gram
equivalent.

Pyrophoric
­
49
CFR
173.124
defines
a
pyrophoric
as
"
a
liquid
or
solid
that,
in
small
quantities
and
without
an
external
ignition
source,
can
ignite
within
five
(
5)
minutes
after
coming
in
contact
with
air."
This
includes
spontaneously
combustible
materials,
water­
reactive
materials,
and
oxidizers.
Examples
of
pyrophoric
radionuclides
are
metallic
plutonium
and
americium.
Examples
of
nonradioactive
pyrophorics
are
organic
peroxides,
sodium
metal,
and
chlorates.
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Quality
Assurance
Project
Plan
(
QAPjP)
­
A
site­
specific
document
that
describes
the
methods
used
by
TRU
waste
generator/
storage
sites
to
comply
with
the
applicable
requirements
for
TRU
waste
characterization
specified
in
the
Waste
Isolation
Pilot
Plant
(
WIPP)
waste
analysis
plan
(
WAP).
The
QAPjP
incorporates
qualitative
or
quantitative
criteria
for
determining
whether
the
waste
characterization
activities
are
being
satisfactorily
performed,
describes
all
activities
pertaining
to
TRU
waste
characterization
required
by
the
WAP,
references
site­
specific
procedural
and
administrative
controls,
and
identifies
organizations
and
positions
responsible
for
implementing
waste
characterization
and
certification
activities.

Radioassay
­
All
types
of
nondestructive
or
destructive
assay
techniques
used
to
identify
and
quantify
radionuclides
in
TRU
waste.
See
also
nondestructive
assay
(
NDA)
and
radiochemical
assay.

Radiochemical
assay
­
Destructive
assay
methods
performed
with
wet
samples
in
a
radiochemical
laboratory
using
separation
techniques.

Radiography
­
A
nondestructive
testing
method,
also
referred
to
as
nondestructive
examination
(
NDE),
that
uses
X­
rays,
gamma
rays,
or
neutrons
to
inspect
and
determine
the
physical
form
of
waste.

Remote­
handled
transuranic
waste
­
Packaged
TRU
waste
whose
external
surface
dose
rate
exceeds
200
mrem
per
hour.
For
the
WIPP,
there
is
an
upper
limit
of
1000
rem
per
hour.

Retrievably
stored
TRU
waste
­
Waste
generated
after
1970
and
before
the
development,
approval,
and
implementation
of
a
TRU
waste
characterization
program
that
meets
the
requirements
for
certification
authority.
TRU
waste
that
is
generated
outside
the
umbrella
of
the
approved
Hanford
Site
TRU
Project
may
be
managed
as
retrievably
stored
TRU
waste
to
demonstrate
compliance
with
applicable
characterization
and
certification
requirements.

Shipper
­
A
TRU
waste
generator/
storage
site
that
releases
a
TRUPACT­
II
cask
to
a
carrier
for
shipment.

Shipping
category
­
A
grouping
system
for
the
transport
of
TRU
waste
payload
containers
that
quantifies
gas
generation
parameters
for
transport
using
the
TRUPACT­
II.

Shipping
package
­
The
packaging
with
its
radioactive
contents,
or
payload,
as
presented
for
transportation
(
10
CFR
71.4).
The
package
is
denoted
as
the
TRUPACT­
II
CH
TRU
waste
shipping
package,
or
equivalently,
the
TRUPACT­
II
shipping
package,
or
TRUPACT­
II
package.

Standard
waste
box
(
SWB)
­
A
payload
container
authorized
for
use
with
TRUPACT­
II
transportation
packages
that
meets
U.
S.
Department
of
Transportation
(
DOT)
Specification
7A
packaging,
or
equivalent,
requirements.
The
SWB
was
designed
specifically
to
fit
TRUPACT­
II.
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PLAN
Summary
category
group
 
Used
to
segregate
TRU­
mixed
wastes
into
broad
groups
having
similar
physical
forms.
The
summary
category
groups
include
homogeneous
solids
(
S3000)
that
are
at
least
50
percent
by
volume
solid
process
residues,
soil/
gravel
(
S4000)
that
is
at
least
50
percent
by
volume
soil/
gravel,
and
debris
(
S5000)
that
is
at
last
50
percent
by
volume
materials
that
meet
the
criteria
specified
in
20.4.1.800
New
Mexico
Administrative
Code
(
incorporating
40
CFR
§
268.2
(
g)).
If
a
waste
does
not
include
at
least
50
percent
of
any
given
category
by
volume,
then
the
summary
category
group
assigned
shall
be
the
same
as
that
constituting
the
greatest
volume
of
waste
for
that
waste
stream.

Ten­
drum
overpack
­
A
specialized
payload
container
authorized
for
use
within
the
TRUPACT­
II
packaging.
One
SWB,
six
85­
gallon
drums,
or
ten
55­
gallon
drums
can
fit
inside
a
ten­
drum
overpack
(
TDOP).
One
TDOP
will
fit
within
the
TRUPACT­
II
packaging.

Tentatively
identified
compounds
(
TICs)
­
Nontarget
compounds
identified
using
GC/
MS.
The
reported
concentrations
for
TICs
will
have
a
higher
uncertainty
associated
with
them
than
the
reported
target
analyte
concentrations.

Test
category
­
Payload
containers
that
do
not
meet
the
analytical
category
decay
heat
limits
or
whose
concentration
of
flammable
VOCs
in
the
headspace
exceeds
500
ppm
are
classified
a
test
category.

Transportation
authority
­
Authorization
for
use
of
the
TRUPACT­
II
or
RH­
TRU
72­
B
cask
for
transportation
of
TRU
waste,
which
is
granted
by
the
permittee
to
those
TRU
waste
generator/
storage
sites
whose
TRU
waste
programs
have
been
evaluated
and
found
to
be
acceptable.

Transuranic
(
TRU)
wastes
­
Wastes
contaminated
with
alpha­
emitting
radionuclides
of
atomic
number
greater
than
92
(
e.
g.,
the
radioactive
isotopes
of
plutonium),
having
half­
lives
greater
than
20
years,
and
present
in
concentrations
greater
than
100
nanocuries
per
gram
of
waste.

TRU
alpha
(
or
 )
activity
concentration
­
The
measured
or
reported
sum
of
the
activities
for
all
TRU
isotopes
with
half­
lives
greater
than
20
years
that
predominately
undergo
alpha
decay
per
unit
mass
of
the
waste.

TRU
isotope
­
Any
isotope
with
an
atomic
number
greater
than
92.
For
purposes
of
calculating
PE­
Ci,
233U
is
treated
as
a
TRU
isotope.

TRU­
mixed
waste
­
TRU
waste
that
is
co­
contaminated
with
hazardous
constituents
as
identified
in
40
CFR
Part
261,
Subparts
C
and
D.

TRU
waste
certification
plan
­
A
site­
specific
document
that
describes
the
methods
used
by
TRU
waste
generator/
storage
sites
to
comply
with
each
TRU
waste
acceptance
criterion
and
requirement
established
in
the
CH­
WAC.
The
certification
plan
shall
include
procedural
and
administrative
controls
and
must
describe
all
activities
pertaining
to
TRU
waste
certification,
including
the
required
QA
and
QC
activities
applicable
to
the
certification
of
TRU
waste.
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PLAN
TRUPACT­
II
­
An
NRC­
certified
Type
B
transportation
packaging
used
for
transportation
of
CH
TRU
wastes.

TRUPACT­
II
packaging
­
The
packaging
consisting
of
an
OCA,
ICV,
and
two
aluminum
honeycomb
spacer
assemblies.

TRUPACT­
II
user
­
Organizations
or
facilities
that
prepare
a
TRUPACT­
II
for
release
to
a
carrier
for
shipment.
Users
ensure,
via
their
TRUPACT­
II
user
program,
that
the
payload,
inspection,
testing,
closing,
and
release
for
shipment
of
the
TRUPACT­
II
meets
the
requirements
of
the
TRUPACT­
II
certificate
of
compliance.
Users
may
also
perform
minor
maintenance
on
the
TRUPACT­
II.

Twist
and
tape
­
A
method
of
bag
closure
for
waste
consisting
of
gathering
the
neck
of
the
bag,
twisting
tightly,
and
wrapping
tightly
with
plastic
tape.
Often
called
"
horsetail."

Validation
­
An
activity
that
demonstrates
or
confirms
that
a
process,
item,
data
set,
or
service
satisfies
the
requirements
defined
by
the
user.
Data
validation
requirements
for
the
TRU
waste
project
are
described
in
the
QAPjP.

Verification
­
The
act
of
authenticating
or
formally
asserting
the
truth
that
a
process,
item,
data
set,
or
service
is
(
in
fact)
that
which
is
claimed.
Data
verification
is
the
process
used
to
confirm
that
all
review
and
validation
procedures
have
been
completed.
Data
verification
requirements
for
the
TRU
waste
project
are
described
in
the
QAPjP.

Visual
examination
(
VE)
technique
­
A
process
of
verification
for
newly
generated
waste
involving
two
independent
verifications
of
the
physical
form
of
the
waste
container
contents.
The
process
consists
of
the
first
operator
confirming
and
documenting
the
contents
(
e.
g.,
inventory)
of
the
container
at
the
time
of
packaging.
A
second
operator
documents
concurrence
of
the
waste
container
contents.
Corrective
actions
are
taken
if
either
the
first
or
the
second
operator
cannot
confirm
the
waste
contents
(
e.
g.,
inventory).

Volatile
organic
compounds
(
VOC)
­
For
the
purposes
of
the
TRU
waste
project,
those
gas
VOCs
listed
in
the
WIPP
Hazardous
Waste
Facility
Permit
Waste
Analysis
Plan
(
WAP)
Table
B­
1
and
any
additional
compounds
tentatively
identified
by
the
VOC
analytical
procedures
used
to
satisfy
TRU
waste
characterization
requirements
specified
in
the
WAP.

Waste
acceptance
criteria
­
Criteria
developed
for
the
safe
disposal
of
TRU
waste
in
the
WIPP,
meeting
the
very
long­
term
disposal
requirements
of
the
WIPP
underground
salt
bed.

Waste
certification
­
Formal
and
documented
activities
associated
with
waste
processing
and
records
required
to
certify
that
the
waste
has
been
characterized
and
meets
the
requirements
of
the
CH­
WAC.

Waste
characterization
­
The
process
of
determining
that
TRU
waste
meets
the
requirements
of
the
CH­
WAC
by
the
acceptable
performance
of
the
activities
defined
by
site­
specific,
permitteeapproved
TRU
waste
project
documents.
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PLAN
Waste
form
­
The
physical
form
of
the
waste
(
e.
g.,
sludge,
combustibles,
metals,
etc.).

Waste
material
type
­
Further
divisions
of
waste
types
based
on
gas
generation
potential
expressed
as
the
G
value
for
hydrogen.

Waste
matrix
code
­
A
DOE­
developed
coding
system
for
grouping
waste
streams
that
have
similar
matrix
constituents,
especially
for
treatment
objectives.
This
coding
system
allows
waste
streams
within
the
DOE
TRU
waste
system
that
have
similar
physical
and
chemical
waste
form
properties
to
be
categorized
together.

Waste
matrix
code
group
­
A
term
used
in
the
WIPP­
WAP
to
group
waste
streams
related
to
physical
and
chemical
properties.

Waste
package
assembly
­
An
assembly
of
waste
packages,
such
as
a
seven­
pack
of
drums
that
is
intended
to
be
handled
and
emplaced
in
a
single
unit
by
the
WIPP
waste
handling
system.

Waste
packaging
­
The
process
of
filling
a
payload
container
with
waste
and
remaining
within
the
controls
applied
to
layers
of
confinement
and
other
WIPP
waste
acceptance
criteria.

Waste
stream
­
Waste
material
generated
from
a
single
process
or
from
an
activity
that
is
similar
in
material,
physical
form,
and
hazardous
constituents.

Waste
type
­
Waste
type
refers
to
physical
types
of
waste
such
as
debris,
soils
and
gravels,
solidified
inorganics,
solid
inorganics,
solidified
organics,
and
solid
organics.
HNF­
2600,
REV
15
Page
16
of
281
5/
11/
2005
HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
1.0
INTRODUCTION
As
a
generator
of
transuranic
(
TRU)
and
TRU
mixed
waste
destined
for
disposal
at
the
Waste
Isolation
Pilot
Plant
(
WIPP),
the
Hanford
site
must
ensure
that
its
TRU
waste
meets
the
requirements
of
U.
S.
Department
of
Energy
(
DOE)
O
435.1,
Radioactive
Waste
Management,
and
DOE/
WIPP­
02­
3122,
Contact­
Handled
Transuranic
Waste
Acceptance
Criteria
for
the
Waste
Isolation
Pilot
Plant
(
CH­
WAC).
CH­
WAC
requirements
are
derived
from
the
WIPP
Technical
Safety
Requirements,
WIPP
Contact
Handled
Documented
Safety
Analysis
(
WIPP
CH­
DSA),
the
transportation
requirements
for
CH­
TRU
wastes
derived
from
the
Transuranic
Package
Transporter­
Model
II
(
TRUPACT­
II)
Certificate
of
Compliance,
WIPP
Land
Withdrawal
Act
(
WIPP­
LWA),
WIPP
Hazardous
Waste
Facility
Permit,
the
U.
S.
Environmental
Protection
Agency
(
EPA)
Compliance
Certification
Decision,
the
initial
Report
for
PCB
Disposal
Authorization,
the
EPA
letter
of
approval
to
land
dispose
non­
liquid
PCBs
at
WIPP
and
the
Revision
to
the
Record
of
Decision
for
the
DOEs
WIPP
Disposal
Phase.
The
CH­
WAC
establishes
the
specific
physical,
chemical,
radiological,
and
packaging
criteria
for
acceptance
of
defense
TRU
waste
shipments
at
WIPP.
The
CH­
WAC
also
requires
that
participating
DOE
TRU
waste
generator/
treatment/
storage
sites
produce
site­
specific
documents,
including
a
certification
plan,
that
describe
their
program
for
managing
TRU
waste
and
TRU
waste
shipments
before
transferring
waste
to
WIPP.
In
addition,
the
QAPD
specifies
the
need
to
develop
a
quality
assurance
(
QA)
plan
that
meets
all
applicable
requirements
of
the
QAPD.
The
Hanford
Site
is
not
implementing
the
use
of
the
HalfPACT,
100­
gallon
drum,
machine
compaction
(
pucks),
payload
management,
S300
pipe
overpacks,
or
controlled
shipments.

Waste
characterization
activities
provide
much
of
the
data
upon
which
certification
decisions
are
based.
Waste
characterization
requirements
for
TRU
waste
and
TRU
mixed
waste
are
established
in
the
WIPP
Hazardous
Waste
Facility
Permit
Waste
Analysis
Plan
(
WIPP­
WAP).
HNF­
2599,
Hanford
Site
Transuranic
Waste
Characterization
Quality
Assurance
Project
Plan,
implements
the
applicable
requirements
in
the
WIPP­
WAP
and
includes
the
qualitative
and
quantitative
criteria
for
making
hazardous
waste
determinations.
The
Hanford
site
must
also
ensure
that
its
TRU
waste
destined
for
disposal
at
WIPP
meets
requirements
for
transport
in
the
Transuranic
Package
Transporter­
II
(
TRUPACT­
II).
The
U.
S.
Nuclear
Regulatory
Commission
(
NRC)
establishes
the
TRUPACT­
II
requirements
in
the
Safety
Analysis
Report
for
the
TRUPACT­
II
Shipping
Package
(
TRUPACT­
II
SAR),
and
the
CH­
TRAMPAC.
Hanford's
QA
packaging
plan
is
defined
in
section
4.0
of
this
Certification
Plan,
consistent
with
10
CFR
Part
71,
Subpart
H.

In
addition,
a
TRU
waste
is
eligible
for
disposal
at
WIPP
only
if
it
has
been
generated
in
whole
or
in
part
by
one
or
more
of
the
activities
listed
in
Section
10101(
3)
of
the
Nuclear
Waste
Policy
Act.
DOE
sites
must
determine
that
each
waste
stream
to
be
disposed
of
at
WIPP
is
"
defense"
TRU
waste.
(
See
also
the
definition
of
"
defense"
TRU
waste.)
Only
CH
TRU
wastes
meeting
the
requirements
of
HNF­
2599,
WIPP­
WAP,
CH­
WAC,
and
other
requirements
documents
described
above
will
be
accepted
for
transportation
and
disposal
at
WIPP.
HNF­
2600,
REV
15
Page
17
of
281
5/
11/
2005
HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
Figure
1­
1
illustrates
the
hierarchy
of
regulatory
requirements
for
TRU
waste
certification
and
reflects
the
flowdown
of
requirements
from
higher­
level
documents
to
site­
level
program
documents
and
implementing
procedures.
To
ensure
future
changes
to
the
CH­
WAC
and
other
relevant
requirements
documents
are
appropriately
reflected,
this
Hanford
Site
Transuranic
Waste
Certification
Plan
(
certification
plan)
will
be
reviewed
at
least
annually
and
updated
as
necessary.

This
certification
plan
establishes
the
programmatic
framework
and
criteria
within
which
the
Hanford
site
ensures
that
CH
TRU
wastes
can
be
certified
as
compliant
with
the
CH­
WAC
and
CH­
TRAMPAC
(
as
applicable).
This
certification
plan
does
not
address
remote­
handled
(
RH)
defense
TRU
forms.
RH
TRU
waste
will
not
be
shipped
or
accepted
at
WIPP
until
it
has
been
addressed.
This
certification
plan
includes
the
following
sections:

 
Section
2.0,
"
Certification
Project
Organization
at
the
Hanford
Site,"
identifies
Hanford
site
organizations
involved
in
the
TRU
waste
certification
project
(
the
project),
describes
the
interaction
between
the
characterization,
certification,
and
transportation
personnel,
and
lists
the
responsibilities
of
key
project
officials.
 
Section
3.0,
"
Compliance
Plan
for
CH­
WAC,"
summarizes
the
CH­
WAC
requirements
and
describes
Hanford
site
TRU
Project
activities
and
specific
documents
that
implement
and
verify
compliance
with
each
requirement.
 
Section
4.0,
"
Compliance
Plan
for
CH­
TRAMPAC,"
summarizes
the
CH­
TRAMPAC
requirements
and
describes
Hanford
site
TRU
Project
activities
and
practices
that
demonstrate
compliance
with
the
TRUPACT­
II
SAR.
 
Section
5.0,
"
Quality
Assurance
Plan,"
describes
how
the
Hanford
site
TRU
Project
complies
with
the
Quality
Assurance
Program
Document,
CH­
WAC,
and
10
CFR
Part
71,
Subpart
H,
QA
requirements
for
TRU
waste
certification
and
use,
maintenance,
and
control
of
packages
used
to
store
and
transport
waste
to
WIPP
in
compliance
with
U.
S.
Department
of
Transportation
(
DOT)
and
NRC
requirements.

This
certification
plan,
which
includes
the
compliance
plan
for
CH­
TRAMPAC
and
associated
QA
plan,
together
with
HNF­
2599
establish
the
basis
for
the
Hanford
site's
TRU
waste
characterization,
certification,
and
transportation
packaging
operations.
The
QA
plan
also
meets
applicable
requirements
of
the
QAPD.
These
documents
are
submitted
to
the
Carlsbad
Field
Office
(
CBFO)
for
review
and
approval.
HNF­
2600,
REV
15
Page
18
of
281
5/
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2005
HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
­­­­­­­­­­­­­­­­­­
Quality
control
requirements
between
documents
Figure
1­
1
­
Hanford
Site
TRU
Waste
Certification
Document
Hierarchy
DOE/
CBFO
WIPP
CH
Documented
Safety
Analysis
(
FEIS,
SEIS
I,
SSEIS
II
QAPD
CH
WAC
NMED
WIPP
Hazardous
Waste
facility
Permit
EPA
WIPP
Compliance
Certification
Decision
WIPP
Approval
for
PCB
Disposal
Hanford
Site
QAPjP
HNF­
2599
Hanford
Site
Certification
Plan
HNF­
2600
TRU
Project
Facility
Procedures
NRC
TRUPACT­
II
Certificates
Of
Compliance
CONGRESS
WIPP
Land
Withdrawal
Act
Energy
&
Water
Development
Appropriations
Act
WIPP
CH­
TRU
Waste
Acceptance
Criteria
HNF­
2600,
REV
15
Page
19
of
281
5/
11/
2005
HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
2.0
CERTIFICATION
PROJECT
ORGANIZATION
AT
THE
HANFORD
SITE
The
responsibilities
for
TRU
waste
management
at
the
Hanford
site
are
distributed
within
various
organizations.
This
section
identifies
the
Hanford
site
organizations
involved
in
the
project
and
describes
the
responsibilities
of
and
interactions
between
these
organizations.
Delegation
of
authority
for
decision
making
will
be
designated
to
the
lowest
appropriate
level
within
the
various
organizations.
This
section
also
contains
generalized
process
flow
diagrams
for
TRU
waste
certification
activities
associated
with
newly
generated
and
retrievably
stored
TRU
waste,
summarizes
the
use
of
acceptable
knowledge
(
AK)
in
the
certification
project,
and
describes
the
document
control
and
records
management
process.

2.1
ORGANIZATION
AND
RESPONSIBILITIES
Figure
2­
1
is
a
functional
organization
chart
pertaining
to
TRU
waste
characterization,
certification,
and
payload
assembly
activities
at
the
Hanford
site.
The
following
subsections
identify
the
organizations
that
oversee
the
project
and
describe
the
roles
and
responsibilities
of
key
positions
within
the
project
charged
with
implementing
the
requirements
defined
in
this
certification
plan.

2.1.1
Office
Director,
CBFO
Office
of
Characterization
and
Transportation
The
Office
Director,
CBFO
Office
of
Characterization
and
Transportation
executes
program
functions
related
to
characterization
of
waste
for
disposal
at
the
WIPP.
The
Office
Director
manages
the
CBFO
Office
of
Characterization
and
Transportation
team,
which
is
responsible
for
TRU
waste
characterization.

The
Office
Director
or
designee
assists
sites
in
preparing
their
waste
for
shipment
to
WIPP
for
disposal.
The
Office
Director
or
designee
develops
options,
recommendations,
and
guidelines
for
program
activities
and
provides
overall
technical
oversight
of
the
TRU
waste
program
activities
at
participating
DOE
sites.
The
Office
Director
or
designee,
in
conjunction
with
the
permittee
QA
manager,
is
responsible
for
conducting
audits
of
all
activities
associated
with
TRU
waste
characterization
and
certification
described
in
the
WIPP
Hazardous
Waste
Facility
Permit
and
associated
WAP
and
QAPD.
The
Office
Director
or
designee
reviews
and
approves
this
certification
plan
before
its
implementation.
The
permittee
QA
manager
also
reviews
and
approves
this
certification
plan.

2.1.2
DOE­
Richland
Operations
Office
The
U.
S.
DOE­
Richland
Operations
Office
(
RL)
Assistant
Manager
for
Central
Plateau
is
responsible
for
project
execution
and
oversight,
and
serves
as
an
interface
between
permittee
and
the
Hanford
site.
The
RL
Project
Director
ensures
that
certification
plan
activities
comply
with
applicable
DOE
orders,
the
WAP,
QAPD,
CH­
WAC,
CH­
TRAMPAC,
and
all
applicable
federal
and
state
regulations.
The
RL
Project
Director
also
ensures
that
resources
and
funding
are
available
to
accomplish
TRU
waste
certification
activities.
HNF­
2600,
REV
15
Page
20
of
281
5/
11/
2005
HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
WSCF
HGS
sampling
(
tech.),
HG
analysis
CWC
Container
management;
HGS
Waste
Serv.

Container
mgmt./
tracking/
status/
resolution,
VE
(
technical)
Director
TRU
Program/
Mgr.
Operations,
SPM
AK
WCO
TCO
RL
Project
Director
PFP
VE
technique,
solid
sampling,
NDA
TRU
Cert.
Supp.
Training,
records,
procedures,
CAM/
DE,
WWIS,
Procurement,
Contracts,
ESL
T
Plant
HGS
Repackaging
QA
Director
Internal
assessments,
QC
test/
inspection
SQAO
FQAO
WRAP
NDA,
NDE,
VE
(
ops),
VE
Technique,
HGS,
TRUPACT­
II,
Repackaging
RL
TRU
Waste
Program
Manager
Figure
2­
1
Hanford
Site
TRU
Waste
Certification
Project
Functional
Organization
Chart
Lines
of
communication
Lines
of
authority
HNF­
2600,
REV
15
Page
21
of
281
5/
11/
2005
HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
2.1.3
Site
Project
Manager
The
site
project
manager
(
SPM)
is
the
principal
point
of
contact
with
DOE
(
including
permittee,
CBFO
Office
of
Characterization
and
Transportation,
and
RL)
for
technical
activities
associated
with
TRU
waste.
The
SPM
provides
programmatic
support
for
Hanford
site
TRU
waste
organizations
involved
in
TRU
waste
storage,
characterization,
certification,
and
transportation
activities.
The
SPM
coordinates
with
the
Hanford
site
waste
certification
official
(
WCO)
and
transportation
certification
official
(
TCO)
and
oversees
project
activities
to
ensure
that
Hanford
site
TRU
waste
is
characterized
and
certified
compliant
with
WIPP
requirements.
Specific
project
responsibilities
assigned
to
the
SPM
include
the
following:

 
Reviewing
and
approving
HNF­
2599
and
this
certification
plan.
 
Ensuring
that
the
Hanford
site
compliance
plan
for
CH­
TRAMPAC
and
associated
documents
are
revised,
reviewed,
approved,
and
implemented
as
necessary
to
maintain
authorization
for
shipping
TRU
waste
to
WIPP.
 
Ensuring
project
personnel
receive
appropriate
training
and
orientation.
 
Selecting,
prioritizing,
and
tracking
waste
to
be
sampled
and
analyzed.
 
Validating
and
verifying
project­
level
analytical
data.
 
Reconciling
analytical
data
with
data
quality
objectives
(
DQOs).
 
Certifying
Waste
Stream
Profile
Form
(
WSPF)
data.
 
Obtaining
AK
information
from
waste
generators
regarding
U.
S.
Environmental
Protection
Agency
(
EPA)
hazardous
waste
numbers.
 
Submitting
quality
assurance/
quality
control
(
QA/
QC)
reports
to
DOE
field
offices.
 
Transmitting
testing,
sampling,
and
analytical
data
to
Carlsbad
Field
Office
(
CBFO),
the
permittee.
 
Assisting
the
Hanford
site
QA
officer
(
SQAO)
in
defining
and
standardizing
project
assessment
criteria
and
preparing
responses
to
deficiency
reports,
such
as
corrective
action
reports
(
CARs),
generated
by
permittee
internal
or
other
external
assessment
organizations.
 
Halting
certification
activities
if
problems
affecting
the
quality
of
certification
processes
or
work
products
exist.
 
Notifying
personnel
of
nonconformances
in
accordance
with
WMP­
400,
Waste
Isolation
Pilot
Plant
Procedures,
Section
1.3.2,
"
TRU
Nonconforming
Item
Reporting
and
Control."

The
SPM
may
delegate
any
of
these
activities
to
another
individual;
however,
the
SPM
retains
responsibility
for
ensuring
that
project
requirements
are
met.
HNF­
2600,
REV
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Page
22
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281
5/
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2005
HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
2.1.4
Hanford
Site
Quality
Assurance
Officer
(
SQAO)

The
SQAO
plans
and
provides
QA
oversight
for
TRU
waste
characterization
and
certification
and
oversees
the
implementation
of
tHNF­
2599
and
the
QA
requirements
of
the
certification
plan.
The
SQAO's
general
responsibilities
include
the
following:

 
Scheduling
and
conducting
QA
assessments.
 
Reviewing
and
approving
HNF­
2599,
this
certification
plan,
and
implementing
procedures.
 
Coordinating
internal
and
external
audits
and
assessments
to
verify
compliance.
 
Reviewing
and
approving
supplier
and
subcontractor
QA
plans
as
appropriate.
 
Tracking
and
evaluating
trends
in
compliance
with
QA
objectives
(
QAOs)
established
in
HNF­
2599
and
Appendix
E
of
this
Certification
Plan
by
performing
the
following:

1.
Ensuring
that
testing,
sampling,
and
analytical
facilities
are
assessed.

2.
Ensuring
that
nonconformance
reports
(
NCRs)
or
CARs
that
affect
project
activities
are
prepared,
when
appropriate.

3.
Tracking
and
trending
nonconformances.

4.
Verifying
corrective
actions
have
been
taken
to
resolve
nonconformances.

5.
Validating
and
verifying
data
at
the
project
level.

6.
Submitting
QA/
QC
reports
to
the
SPM,
as
needed.

7.
Preparing
and
submitting
semiannual
QA
summary
reports
to
the
SPM.

 
Coordinating
responses
to
deficiency
reports
(
e.
g.,
CARs)
generated
by
permittee
or
other
external
assessment
organizations.
 
Providing
QA
oversight
for
data
package
assembly
and
interface
with
the
WIPP
Waste
Information
System
(
WWIS).
 
Stopping
certification
activities
if
problems
affecting
the
quality
of
certification
processes
or
work
products
exist.
 
Having
direct
access
to
responsible
management
at
a
level
where
appropriate
action
can
be
affected.
 
Being
sufficiently
independent
from
cost
and
schedule
considerations.
 
Having
the
organizational
freedom
to
communicate
with
management.
 
Having
no
assigned
responsibilities
unrelated
to
the
QA
program
that
would
prevent
appropriate
attention
to
QA
matters.
 
Developing,
establishing,
and
interpreting
QA
policy,
and
ensuring
effective
implementation.
 
Interfacing,
as
appropriate,
with
the
permittee
staff,
participants,
and
other
stakeholders
on
QA
matters.
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HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
 
Assisting
subordinate
organizations
with
quality
planning,
documentation,
quality
measurements,
and
problem
identification
and
resolution.
 
Providing
guidance
to
all
applicable
subordinate
organizations
concerning
identification,
control,
and
protection
of
QA
records.

The
SQAO
may
designate
one
or
more
individuals
to
perform
the
above
functional
responsibilities
but
retains
ultimate
responsibility
for
ensuring
compliance
with
project
requirements.

2.1.5
Hanford
Site
Waste
Certification
Official
(
WCO)

The
Hanford
site
WCO
is
responsible
for
certifying
all
data
and
information
necessary
to
document
that
all
TRU
waste
payload
containers
prepared
for
shipment
to
WIPP
meet
all
specified
criteria.
The
WCO
coordinates
activities
related
to
waste
characterization
and
works
closely
with
the
SQAO
to
effect
QC
of
the
project.
Specific
duties
and
responsibilities
of
the
WCO
include
the
following:

 
Certifying
that
waste
packages
meet
CH­
WAC
requirements.
 
Interfacing
with
the
SPM,
TCO,
and
SQAO
on
matters
related
to
waste
characterization
and
certification.
 
Implementing
the
following
project
QA
activities:

1.
Reviewing
and
approving
this
certification
plan.

2.
Ensuring
that
waste
characterization
and
certification
documents
are
managed
as
QA
records
in
the
designated
repository.

3.
Preparing
NCRs
and
CARs,
and
documenting
corrective
actions.

4.
Coordinating
with
the
SQAO
to
analyze
trends
in
project
nonconformances
for
waste
characterization­
related
activities.

5.
Assisting
the
SQAO
in
preparing
responses
to
deficiency
reports
(
e.
g.,
CARs)
generated
by
permittee
or
other
external
assessment
organizations.

 
Stopping
waste
characterization
activities
if
problems
affecting
the
quality
of
certification
processes
or
work
products
exist.
 
Ensuring
the
data
on
characterization
and
certification
entered
into
the
WWIS
are
accurate
and
demonstrate
the
acceptability
of
the
waste
for
transport
to
and
disposal
at
the
WIPP.

The
WCO
may
designate
one
or
more
individuals
to
perform
these
responsibilities
but
retains
ultimate
responsibility
for
ensuring
that
project
requirements
are
met.
HNF­
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HANFORD
SITE
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WASTE
CERTIFICATION
PLAN
2.1.6
Hanford
Site
Transportation
Certification
Official
(
TCO)

The
Hanford
site
TCO
ensures
that
the
site­
specific
TRU
waste
packaging
and
transportation
activities
comply
with
the
CH­
TRAMPAC,
and
DOT
requirements
specified
in
49
CFR
173
and
NRC
requirements
in
10
CFR
71.
The
TCO
verifies
payload
containers
and
payload
assemblies
and
ensures
compliance
with
all
packaging
and
records
requirements.
The
TCO
obtains
WIPP
authority
to
ship
and
ensures
that
all
requirements
are
met
before
the
transportation
packaging
is
released
to
a
carrier
for
transport.
Specific
TCO
responsibilities
include
the
following:

 
Ensuring
that
the
Hanford
site
compliance
plan
for
CH­
TRAMPAC
and
associated
documents
are
revised,
reviewed,
approved,
and
implemented,
as
necessary,
for
the
Hanford
site
to
maintain
authorization
for
offsite
shipments
of
TRU
waste.
 
Interfacing
with
the
originating
facility
to
develop
and
maintain
procedures
to
load
the
TRUPACT­
II
in
accordance
with
the
TRUPACT­
II
SAR,
CH­
TRAMPAC,
and
CH­
WAC
to
ensure
that
all
payloads
meet
all
applicable
requirements.
 
Maintaining
Hanford
site
content
codes
in
accordance
with
the
CH­
TRUCON
document,
and
requesting
revisions
from
CBFO,
as
necessary.
 
Interfacing
with
the
SPM,
WCO,
and
SQAO
on
matters
related
to
payload
certification
and
offsite
transportation
of
TRU
waste.
 
Reviewing
and
approving
this
certification
plan.
 
Reviewing
all
payload
data
sheets,
and
documenting
compliance
with
all
packaging
and
shipping
requirements
described
in
this
certification
plan.
 
Preparing
and
signing
bills
of
lading,
uniform
hazardous
waste
manifests
(
UHWM),
and
land
disposal
restriction
(
LDR)
notifications,
as
appropriate.

Shipping
activities
related
to
the
TRUPACT­
II
and
WIPP
acceptance
include
the
following:

 
Ensuring
compliance
with
applicable
DOT
and
NRC
regulations.
 
Providing
guidance
to
waste
generators
to
assist
their
efforts
to
comply
with
the
CHTRAMPAC
and
CH­
WAC
criteria
and
requirements
in
implementing
procedures
affecting
characterization,
QA,
and
waste
certification.
 
Ensuring
that
the
proper
shipping
category,
content
code,
and
waste
form
are
assigned
to
each
container
and
shipment.
 
Reviewing
all
payload
data
sheets
and
Hanford
site
records
to
guarantee
and
document
compliance
with
all
packaging
and
shipping
requirements.
 
In
conjunction
with
the
WCO,
ensuring
all
waste
containers
and
shipments
are
certifiable
for
transport
and
all
documentation
packages
are
complete
and
accurate.
 
Ensuring
all
data
entered
into
the
WWIS
is
accurate
and
demonstrates
the
acceptability
of
the
waste
for
transport
to
and
disposal
at
the
WIPP.
 
Approving
by
signature
on
the
transportation
certification
documents
for
every
payload.
 
Completing
PCTCD,
OPCTCD,
and
PATCD
and
preparing
shipping
data.
 
Providing
guidance
to
loading
personnel
for
assembling
and
loading
payload
containers.
 
Entering
final
shipping
data
into
WWIS.
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HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
The
TCO
may
designate
one
or
more
individuals
to
perform
these
responsibilities
but
retains
ultimate
responsibility
for
ensuring
that
certification­
related
project
requirements
are
met.

2.2
WASTE
CHARACTERIZATION/
CERTIFICATION
PROCESS
The
Hanford
site
TRU
waste
process
for
characterizing
and
certifying
waste
and
preparing
it
for
transport
to
WIPP
involves
a
series
of
operations
based
on
whether
the
waste
is
retrievably
stored
or
newly
generated
and
the
physical
form
of
the
waste.
Newly
generated
TRU
waste
is
defined
as
TRU
waste
generated
after
the
New
Mexico
Environment
Department
(
NMED)
notifies
WIPP,
by
approval
of
the
final
audit
report,
that
the
Hanford
site
has
satisfactorily
implemented
the
characterization
requirements
of
the
WAP.

Initially,
acceptable
knowledge
(
AK)
is
used
to
delineate
all
TRU
waste
containers
into
waste
streams
and
assign
an
appropriate
waste
matrix
code
group
category
based
on
the
physical
form
of
the
waste
and
the
waste
contents.
AK
is
also
used
to
make
determinations
regarding
EPA
hazardous
waste
numbers,
radionuclide
composition,
and
prohibited
item
restrictions.
AK
information
for
each
waste
stream
is
assessed
and
verified
through
evaluation
of
results
from
applicable
testing,
sampling,
and
analytical
activities.

Waste
characterization
requirements
for
retrievably
stored
and
newly
generated
wastes
differ,
as
summarized
below.

 
Radiography
and/
or
visual
examination
(
VE)
are
used
to
identify
and/
or
confirm
the
waste
matrix
code
group
category
and
waste
material
parameter
designations
and
identify
prohibited
items.
All
retrievably
stored
waste
containers
undergo
radiography.
Radiography
is
confirmed
by
VE
on
a
randomly
selected
number
of
containers
in
each
retrievably
stored
waste
stream.
For
newly
generated
waste,
physical
form
and
prohibited
items
are
verified
during
packaging
using
the
VE
technique.
The
VE
technique
is
not
the
same
process
as
VE
that
is
performed
to
verify
radiography.
The
VE
technique
involves
two
independent
verifications
of
the
physical
form
of
the
waste
and
contents
at
the
time
of
packaging.
The
first
operator
documents
the
content
of
the
waste
container,
providing
a
written
inventory
of
actual
or
estimated
weights
of
each
item
place
in
the
container.
The
operator
also
documents
that
prohibited
article(
s)
are
not
present.
A
second,
independent
operator
provides
additional
verification
by
reviewing
the
waste
contents
and
ensuring
correct
reporting
of
the
waste
container
content.
Corrective
actions
are
taken
if
either
the
first
or
second
operator
cannot
independently
confirm
the
waste
designations.
 
Radioassay
data
identify
and
quantify
radionuclide
composition
and
concentration.
All
TRU
waste
containers
from
newly
generated
and
retrievably
stored
waste
streams
undergo
radioassay.
 
Headspace­
gas
sampling
and
analysis
provide
data
to
determine
potential
flammability
and
confirm
EPA
hazardous
waste
numbers
of
each
waste
container.
All
TRU
waste
containers
from
newly
generated
and
retrievably
stored
waste
streams
or
randomly
selected
containers
from
waste
streams
that
meet
the
conditions
for
reduced
headspacegas
sampling
listed
in
HNF­
2599,
Section
B­
3a(
1),
undergo
headspace­
gas
sampling
and
analysis.
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HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
 
Sampling
and
analysis
of
homogeneous
wastes
provide
data
to
confirm
listed
and
toxicity
characteristic
EPA
hazardous
waste
numbers
and
quantify
hazardous
constituent
concentration.
The
RCRA­
regulated
constituents
in
newly
generated
homogeneous
solid
waste
streams
are
documented
and
verified
at
the
time
of
generation
based
on
AK
and
sampling
and
analysis.
For
continuous
processes
that
result
in
newly
generated
homogeneous
wastes
(
except
soil/
gravel
waste
streams),
initial
sampling
is
conducted,
and
process
control
parameters
are
established
to
develop
a
baseline
control
chart
for
the
process.
The
parameter
limits
for
a
waste­
generating
process
are
established
in
specific
written
procedures
for
the
process.
Process
performance
relative
to
the
established
parameter
limits
is
determined
through
annual
sampling
of
the
process,
which
is
conducted
on
a
random
basis.
If
the
parameter
limits
are
exceeded,
the
waste
stream
is
recharacterized
according
to
procedures
and
methods
specified
for
retrievably
stored
waste.
In
cases
where
control
charting
is
not
useful
in
controlling
hazardous
waste
constituents,
homogeneous
wastes
are
characterized
in
process
batches
as
described
in
HNF­
2599,
section
B­
3d(
1)(
a).
The
number
of
newly
generated
soil/
gravel
waste
containers
to
be
randomly
sampled
and
analyzed
is
determined
through
a
statistical
selection
process.
Using
a
similar
approach,
a
statistically
selected
portion
of
retrievably
stored
homogeneous
solids
and
soil/
gravel
wastes
are
sampled
and
analyzed
to
confirm
waste
constituents.
 
On
a
case­
by­
case
basis,
in
consultation
with
the
CBFO,
certain
waste
streams
may
be
characterized
using
sampling
and
analysis
results
from
another
TRU
waste
generator/
storage
site
that
has
received
certification
authority
from
CBFO.
Homogeneous
waste
solid
sampling
and
analysis,
headspace­
gas
sampling
and
analysis,
radioassay,
and
radiography/
visual
examination
are
all
examples
of
characterization
techniques
that
may
be
performed
by
other
sites.
The
data
will
be
useable
to
certify
waste
so
long
as
it
was
gathered
using
plans
and
procedures
that
have
been
evaluated
through
an
audit
conducted
by
CBFO
and
deemed
to
meet
the
requirements
of
the
WIPP
Hazardous
Waste
Permit,
QAPD,
and
CH­
WAC.

Radioassay
and
analytical
facilities
(
i.
e.,
headspace
gas
and
homogeneous
waste
stream
analysis)
are
qualified
through
participation
in
the
applicable
performance
demonstration
program
(
PDP).
The
PDP
program
supports
the
determination
of
a
facility
to
meet
QA
objectives.

The
SPM
reconciles
waste
characterization
data
against
applicable
data
quality
objectives
(
DQOs).
Data
quality
objectives
are
qualitative
and
quantitative
statements
that
specify
WIPP
program
technical
and
quality
objectives.
DQOs
are
determined
through
the
DQO
process.
The
DQOs
for
the
waste
characterization
activities
are
contained
in
the
WAP,
attachment
B3
and
Subsection
3.3
and
Appendix
E
of
this
Certification
Plan.

On
a
case­
by­
case
basis,
in
consultation
with
CBFO,
the
SPM
may
choose
to
accept
data
validation
and
verification
and
DQO
reconciliation
performed
by
other
sites
that
have
been
granted
waste
certification
authority
by
CBFO.
HNF­
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HANFORD
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WASTE
CERTIFICATION
PLAN
Figures
2­
2a
through
2­
2f
and
2­
3a
through
2­
3e
illustrate
the
typical
process
flow
for
retrievably
stored
and
newly
generated
TRU
waste,
respectively.
Certain
characterization
activities
identified
for
retrievably
stored
waste
may
be
applied
to
newly
generated
waste
and
vice
versa,
provided
that
compliance
with
waste
characterization
requirements
can
be
adequately
demonstrated.
In
addition,
variance
from
the
depicted
flow
path
within
each
process
may
be
necessary
to
address
technical
or
operational
needs.
Sections
3.0
and
4.0
detail
the
methods
of
compliance
and
verification
for
each
certification­
related
process
and
identify
applicable
implementing
procedures.

2.2.1
Waste
Stream
Documentation
Hanford
site
waste
generators
produce
waste
stream
documentation
to
meet
Hanford
site
waste
acceptance
criteria
and
support
the
waste
stream
approval
process.
Waste
stream
information
is
supplied
on
site­
specific
forms
and
attachments.
At
a
minimum,
generators
provide
the
following
waste
stream
information:

 
Generator
information
 
Waste
stream
name
 
Waste
generating
process
description
 
Radiological
information
(
e.
g.,
classification,
reportable
radionuclides,
characterization
method)
 
Chemical
constituent
information
(
e.
g.,
chemicals
present,
concentration
ranges,
characterization
methods)
 
Land
disposal
restriction
(
LDR)
information,
including
identification
of
underlying
hazardous
constituents,
if
applicable
 
Waste
type
information
(
e.
g.,
physical
state,
inert
materials,
and
stabilizing
agents
and/
or
absorbents
used)
 
Packaging
information
(
e.
g.,
container
type
and
size,
maximum
weight)
 
Additional
attachments,
including
process
flow
information,
analytical
data,
container
drawings,
or
other
waste
acceptance
information.
HNF­
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HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
Figure
2­
2a.
Certification
Flow
for
Retrievably
Stored
TRU
Waste.
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HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
Yes
Yes
Yes
No
No
No
Figure
2­
2b.
Certification
Flow
for
Retrievably
Stored
TRU
Waste
(
continued)

Repackage
compliant
waste
Remove
noncompliant
waste
items
NDE
Criteria
 
Verify
waste
contents
 
Identify
prohibited
waste
items
 
Verify
correct
packaging
 
Estimate
waste
material
parameter
weights.
Go
to
Figure
2­
2c
NDE
Data
Package
 
Waste
matrix
code
 
Content
description
 
Number
of
layers
of
packaging
 
Waste
material
parameter
weights
NDA
Data
Package
 
Pu­
239
FGE
 
PE­
Ci
 
Isotopic
composition
and
concentration
 
Wattage
(
decay
heat)

Incoming
waste
containers
from
Figures
2­
2a,
2­
2d,
or
2­
2e
Does
NDE
confirm
that
waste
container
meets
WIPP
criteria?

NDA
for
glovebox
waste
acceptance
NOTE
 
If
waste
is
LLW,
remove
from
TRU
Program
NDA
Criteria
 
Calculate
Pu­

239
FGE
 
Determine
radionuclide
composition
and
concentration
 
Determine
TRU
alpha
activity
 
Calculate
decay
heat
Does
NDA
confirm
that
waste
container
meets
WIPP
criteria?

Is
waste
low
level?

CERTIFICATION
INFORMATION
Remove
waste
from
TRU
Programs
HNF­
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CERTIFICATION
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Figure
2­
2c.
Certification
Flow
for
Retrievably
Stored
TRU
Waste
(
continued)
HNF­
2600,
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31
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HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
Figure
2­
2d.
Certification
Flow
for
Retrievably
Stored
TRU
Waste
(
continued)
HNF­
2600,
REV
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32
of
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HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
Figure
2­
2e.
Certification
Flow
for
Retrievably
Stored
TRU
Waste
(
continued)
HNF­
2600,
REV
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33
of
281
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HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
Figure
2­
2f.
Certification
Flow
for
Retrievably
Stored
TRU
Waste
(
concluded)
HNF­
2600,
REV
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34
of
281
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HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
Figure
2­
3a.
Certification
Flow
for
Newly
Generated
TRU
Waste
HNF­
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REV
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HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
Figure
2­
3b.
Certification
Flow
for
Newly
Generated
TRU
Waste
(
Continued)
HNF­
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36
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HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
Figure
2­
3c.
Certification
Flow
for
Newly
Generated
TRU
Waste
(
Continued)
HNF­
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37
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HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
Figure
2­
3d.
Certification
Flow
for
Newly
Generated
TRU
Waste
(
Continued)
HNF­
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38
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HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
Figure
2­
3e.
Certification
Flow
for
Newly
Generated
TRU
Waste
(
Concluded)
HNF­
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HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
Information
supplied
by
waste
generators
is
supplemented
with
information
gathered
during
TRU
Project
characterization
and
certification
activities
to
meet
data
requirements
for
completing
the
permittee
Waste
Stream
Profile
Form
(
WSPF)
and
WWIS
submittals.

2.2.2
Acceptable
Knowledge
Documentation
The
Hanford
site
uses
AK
to
assign
waste
matrix
code
groups,
content
codes,
and
EPA
hazardous
waste
numbers
and
to
determine
the
waste
material
parameters
and
radionuclides
present
in
waste
streams.
For
each
TRU
waste
stream
(
and/
or
waste
stream
lot),
AK
information
is
compiled
in
an
auditable
record;
confirmed
through
radiography,
VE,
VE
technique,
radiological
assay,
headspace­
gas
sampling
and
analysis,
and
homogeneous
waste
sampling
and
analysis
(
applicable
to
homogeneous
solids
and
soil/
gravel
waste
streams
only);
and
audited
periodically
to
ensure
adequacy
of
the
information.

Information
compiled
to
document
AK
on
a
site­
wide
and
facility­
specific
basis
includes
TRU
waste
management
project
information,
waste
stream
information,
and
supplemental
documentation
(
including
reference
lists),
as
needed.
The
SPM
(
or
designee)
reviews
waste
stream
documentation
and
data
packages
resulting
from
radiography,
VE,
VE
technique,
headspace­
gas
sampling
and
analysis,
and
solidified
waste
sampling
and
analysis
(
as
appropriate)
to
confirm
waste
matrix
code
group
designations,
EPA
hazardous
waste
numbers,
and
waste
material
parameter
designations
using
AK.
Changes
to
EPA
hazardous
waste
numbers
are
identified
and
justified
based
on
confirmatory
testing
data.
AK
information
is
reevaluated
if
discrepancies
are
identified
between
AK
documentation
and
data
from
confirmatory
testing.

2.2.3
Waste
Characterization
and
Certification
Data
Reporting
The
SPM
(
or
designee)
reconciles
TRU
waste
characterization
data
with
DQOs
and
completes
a
WSPF
for
each
Hanford
site
TRU
waste
stream
to
be
disposed
at
the
WIPP.
Summaries
of
waste
stream
information
and
reconciliation
of
DQOs
comprise
WSPF
attachments.
WMP­
400,
Section
7.1.1,
"
Transuranic
Waste
Characterization
Data
Quality
Objectives
Reconciliation
and
Reporting,"
specifies
the
information
required
to
complete
the
WSPF
and
describes
the
process
for
reconciling
waste
characterization
data
with
project­
required
parameters,
preparing
data
summary
reports,
and
correlating
container
identification
to
data
packages.

Before
shipping
TRU
waste
containers
from
a
WIPP­
accepted
and
approved
waste
stream,
the
SPM
transmits
waste
characterization,
certification,
and
shipment
data
to
the
WIPP
using
the
WWIS.
Only
data
that
is
finalized
and
been
through
all
the
data
validation
steps
can
be
entered
in
WWIS.
WWIS
contains
limit
and
edit
checks
on
some
of
the
WAC
requirements
and
assists
WIPP
in
determining
that
waste
is
acceptable
for
disposal
at
WIPP.
WMP­
400,
Section
7.1.5,
"
WIPP
Waste
Information
System
Data
Entry
and
Reporting,"
describes
the
process
for
entering
and
reporting
required
data
on
payload
containers
and
assemblies
into
the
WWIS.
WIPP
will
only
accept
waste
container
shipments
for
disposal
if
the
waste
container
information
has
been
correctly
submitted
to
the
WWIS
and
approved
for
shipment
by
the
WIPP
data
administrator.
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2.2.4
Qualification
of
Existing
Data
The
qualification
process
shall
be
conducted
in
accordance
with
approved
procedures
that
provide
for
documentation
of
the
decision
process,
the
factors
used
in
arriving
at
the
choice
of
the
qualification
method,
and
the
decision
that
the
data
are
qualified
for
their
intended
use.
Existing
data
shall
be
qualified
using
one
or
a
combination
of
the
following
methods:

1.
Determination
that
the
data
were
collected
under
a
QA
program
that
is
equivalent
in
effect
to
ASME
NQA­
1­
1989
edition;
ASME
NQA­
2a­
1990
addenda,
Part
2.7,
to
ASME
NQA­
2­
1989
edition;
and
NQA­
3­
1989.
Factors
to
be
considered
include:

a.
Qualifications
of
personnel
or
organizations
generating
data
b.
Technical
adequacy
of
the
equipment
and
procedures
used
to
collect
and
analyze
the
data
c.
Environmental
conditions
under
which
the
data
were
obtained
(
if
germane)

d.
Quality
and
reliability
of
the
measurement
control
program
under
which
the
data
were
generated
e.
Extent
to
which
data
demonstrate
properties
of
interest
(
e.
g.,
physical,
chemical,
geologic,
or
mechanical)

f.
Extent
to
which
conditions
generating
the
data
may
partially
meet
requirements
of
DOE­
CBFO
94­
1012
g.
Prior
uses
of
the
data
and
the
associated
verification
processes
h.
Prior
peer
or
other
professional
reviews
of
data
and
their
results
i.
Extent
and
reliability
of
the
documentation
associated
with
the
data
j.
Extent
and
quality
of
corroborating
data
or
confirmatory
testing
results
k.
Degree
to
which
data
generating
processes
were
independently
audited
l.
The
importance
of
the
data
in
showing
that
the
repository
design
meets
the
performance
objectives
2.
The
use
of
corroborating
data,
with
the
data
relationships
and
inferences
clearly
identified
and
justified.

3.
Confirmatory
testing
that
is
performed
and
documented.
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PLAN
4.
Peer
review
conducted
in
a
manner
that
is
compatible
with
NUREG­
1297,
Peer
Review
for
High­
Level
Nuclear
Waste
Repositories.

a.
Peer
reviews
shall
be
performed
when
the
adequacy
of
information
or
the
suitability
of
procedures
and
methods
essential
to
showing
that
a
repository
system
meets
its
performance
requirements
with
respect
to
safety
and
calculations,
or
reference
to
previously
established
standards
and
practices.

b.
Peer
reviews
performed
in
support
of
WIPP
compliance
activities
shall
be
documented,
as
shall
all
peer
review
processes
5.
Peer
reviews
are
used
for
the
following
activities:

a.
Conceptual
models
selected
and
developed
by
DOE
b.
Waste
characterization
analysis
as
required
in
40
CFR
194.24(
b)

c.
Engineered
barrier
evaluation
as
required
in
40
CFR
194.44.

2.3
CERTIFICATION
PROJECT
DOCUMENT
CONTROL
AND
RECORDS
MANAGEMENT
This
certification
plan,
which
includes
the
compliance
plan
for
CH­
TRAMPAC
and
associated
QA
plans,
together
with
HNF­
2599
establish
the
basis
for
the
Hanford
site's
TRU
waste
characterization,
certification,
and
transportation
packaging
operations.
These
documents
are
submitted
to
permittee
for
review
and
approval.
The
individuals
identified
in
table
2­
1
review
and/
or
approve
this
certification
plan
and
any
revisions.
The
SPM
(
or
designee)
reviews
this
certification
plan
at
least
annually
and
schedules
revisions,
reviews,
approvals,
and
distribution.

Table
2­
1
Review,
Approval,
and
Control
Requirements
for
the
Hanford
Site
Certification
Plan
Organization/
Reviewer
Review
and
approval
Change
approval
Change
control
Office
Director,
CBFO
Office
of
Characterization
and
Transportation
X
Xa
 
Carlsbad
Field
Office
Quality
Assurance
Manager
X
X
 
Site
Project
Manager
X
X
Xb
Site
Quality
Assurance
Officer
X
X
 
Waste
Certification
Official
X
X
 
Transportation
Certification
Official
X
X
 
Note:
 
=
not
required.
aChanges
affecting
performance
criteria
or
data
quality
only.
bEnsures
compliance
with
records
management
requirements.
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HANFORD
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PLAN
Project
personnel
develop,
maintain,
and
control
this
certification
plan
in
accordance
with
WMP­
400,
Section
1.4.1,
"
TRU
Document
Control."
Project
personnel
generate
records
of
characterization,
certification,
packaging,
and
transportation
activities
and
review
these
records
to
ensure
compliance
with
project
requirements.
Records
are
collected,
processed,
stored,
and
maintained
in
accordance
with
records
management
requirements
established
in
WMP­
400,
Section
1.5.1,
"
TRU
Records
Management."

3.0
COMPLIANCE
PLAN
FOR
CH­
WAC
This
section
describes
how
the
Hanford
site
complies
with
the
requirements
and
associated
criteria
for
WIPP
acceptance
of
CH
TRU
waste,
including
transportation
safety
requirements
(
e.
g.,
acceptable
methods
for
payload
compliance)
defined
in
the
TRUPACT­
II
Certificates
of
Compliance,
WIPP
Hazardous
Waste
Facility
Permit
requirements
for
TRU
mixed
waste
established
in
the
WAP,
and
EPA
environmental
compliance
requirements
established
in
the
40
CFR
191/
194,
Compliance
Certification
Decision,
the
Initial
Report
for
PCB
Disposal
Authorization,
the
letter
of
approval
to
land
dispose
non­
liquid
PCBs
at
WIPP,
the
Revision
to
the
Record
of
Decision
for
the
DOE's
WIPP
Disposal
Phase,
and
the
Energy
and
Water
Development
Appropriations
Act,
the
Contact­
handled
Documented
Safety
Analysis.

CH­
WAC
requirements
are
organized
under
five
major
categories:
1)
container
properties,
2)
radiological
properties,
3)
physical
properties,
4)
chemical
properties,
and
5)
data
package
contents.

Subsections
3.1
through
3.6
correlate
with
the
organization
in
the
CH­
WAC
for
CH
TRU
waste
requirements
and
identify
methods
of
compliance
to
meet
each
requirement.
Procedures
that
implement
the
process
controls,
techniques,
tests,
and
other
actions
to
be
applied
to
each
TRU
payload
container,
waste
stream,
and
shipment
are
also
identified.
Appendix
A
summarizes
the
CH­
WAC
and
CH­
TRAMPAC
requirements
and
identifies
the
Hanford
site
documents
and
procedures
that
implement
each
requirement.
The
numbering
of
CH­
WAC
requirements
in
Appendix
A
correlates
with
the
numbering
system
in
the
following
subsections.
Waste
shipped
to
WIPP
must
comply
with
the
most
restrictive
of
the
CH
TRU
requirements
established
in
the
CH­
WAC
and
CH­
TRAMPAC.
Therefore,
only
the
most
restrictive
requirements
are
described
in
this
subsection.
In
addition,
because
many
CH­
WAC
and
CH­
TRAMPAC.
requirements
overlap,
this
subsection
refers
to
section
4.0
of
this
Certification
Plan,
where
appropriate,
for
applicable
methods
of
compliance
and
verification
for
both
CH­
WAC
and
CH­
TRAMPAC
requirements.

3.1
SUMMARY
OF
WIPP
AUTHORIZATION
BASIS
Revisions
of
requirements
in
referenced
documents
controlled
by
agencies
or
organizations
other
than
DOE
(
e.
g.,
EPA,
NMED,
NRC)
shall
have
precedence
over
values
quoted
in
this
certification
plan.
Changes
incorporated
in
future
revisions
of
the
CH­
WAC
will
be
reflected
in
future
revisions
of
this
certification
plan.
Requests
for
exceptions
(
variances)
to
requirements
must
be
submitted
formally
to
the
permittee
for
approval.
The
permittee
cannot
approve
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exceptions
(
variances)
to
external
requirements
that
are
controlled
by
organizations
other
than
DOE
without
first
obtaining
changes
to
the
controlling
authorizations.

Only
waste
that
is
preceded
by
an
approved
WSPF
will
be
shipped
to
WIPP.
Only
payload
containers
from
a
properly
characterized
and
approved
waste
stream
can
be
certified
as
meeting
the
requirements
and
associated
criteria
in
this
certification
plan.
The
Hanford
site
shall
submit
characterization,
certification,
and
shipping
data
to
WIPP
using
the
WWIS
before
shipment
of
that
waste.
Any
payload
containers
with
unresolved
discrepancies
associated
with
hazardous
waste
characterization
will
not
be
managed
or
disposed
at
WIPP
until
the
discrepancies
are
resolved
in
accordance
with
requirements
established
in
the
WAP.
Corrective
action
reports
applicable
to
WAP
requirements
shall
be
resolved
before
waste
shipment.
Throughout
this
subsection
and
the
discussions
of
compliance
and
verification
methods,
it
can
be
assumed,
unless
otherwise
noted,
that
if
a
requirement
is
not
met,
project
personnel
will
segregate
the
nonconforming
item
and
initiate
an
NCR
or
CAR
in
accordance
with
WMP­
400,
Section
1.3.2,
"
TRU
Nonconforming
Item
Reporting
and
Control,"
or
WMP­
400,
Section
1.3.3,
"
TRU
Corrective
Action
Reporting
and
Control."
Corrective
action
will
be
taken
in
accordance
with
WMP­
400,
Section
1.3.1,
"
TRU
Corrective
Action
Management,"
to
resolve
nonconformances.
Also
see
subsection
5.3
of
this
certification
plan
for
more
details
about
the
NCR/
CAR
process.

3.1.1
DOE
Operations
and
Safety
Requirements
for
WIPP
3.1.1.1
Requirements
The
WIPP
CH­
DSA
addresses
CH
TRU
waste
handling
and
emplacement
operations
at
the
WIPP
site.
The
waste
accepted
for
emplacement
in
the
WIPP
must
conform
to
the
WIPP
CH­
DSA
and
the
associated
technical
safety
requirements.
The
WIPP
CH­
DSA
documents
the
safety
analyses
that
develop
and
evaluate
the
adequacy
of
the
WIPP
safety
bases
necessary
to
ensure
the
safety
of
workers,
the
public,
and
the
environment
from
the
hazards
posed
by
WIPP
waste
receiving,
handling,
and
emplacement
operations.
The
WIPP
CH­
DSA
establishes
and
evaluates
the
adequacy
of
the
safety
bases
in
response
to
plant
normal
and
abnormal
operations
and
postulated
accident
conditions.

3.1.1.2
Compliance
and
Verification
CH
waste
sent
to
WIPP
will
be
certified
in
accordance
with
the
requirements
of
HNF­
2599
(
Hanford
Site
Transuranic
Waste
Characterization
Quality
Assurance
Project
Plan
and
this
Certification
Plan.
Thus,
waste
containers
certified
by
Hanford
will
be
compliant
with
the
WIPP
CH­
DSA
and
associated
technical
safety
requirements.

3.1.2
NRC
Transportation
Safety
Requirements
for
the
TRUPACT­
II
3.1.2.1
Requirements
Acceptable
methods
for
payload
compliance
are
defined
in
the
TRUPACT­
II
Certificates
of
Compliance
(
C
of
C)
and
implemented
by
the
CH­
TRAMPAC.
For
shipments
to
WIPP,
a
site­
specific
CH­
TRAMPAC,
Section
4.0
of
this
Certification
Plan,
will
be
prepared
describing
how
it
will
ensure
compliance
with
each
payload
parameter.
This
site­
specific
CH­
TRAMPAC
HNF­
2600,
REV
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HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
shall
contain
sufficient
detail
to
allow
reviewers
to
adequately
understand
and
evaluate
the
compliance
methodology
for
each
payload
parameter.

A
packaging
QA
program
that
defines
the
QA
activities
that
apply
to
the
use
of
NRC­
approved
transportation
packagings
equivalent
to
10
CFR
Part
71,
Subpart
H,
shall
be
prepared.

3.1.2.2
Compliance
and
Verification
CH
waste
sent
to
WIPP
will
be
certified
in
accordance
with
HNF­
2599
and
HNF­
2600
requirements.
Section
4.0
of
this
Certification
Plan
outlines
the
site­
specific
CH­
TRAMPAC
requirements
to
meet
NRC
transportation
safety
requirements
for
use
of
the
TRUPACT­
II
shipping
vessel.
A
site­
specific
QA
plan
is
outlined
in
section
5.0
of
this
Certification
Plan,
consistent
with
10
CFR
Part
71,
Subpart
H.

3.1.3
NMED
Hazardous
Waste
Facility
Permit
Requirements
3.1.3.1
Requirements
TRU
waste
is
classified
as
TRU
mixed
waste
if
it
contains
hazardous
constituents
regulated
under
Resource
Conservation
and
Recovery
Act
(
RCRA).
Only
TRU
mixed
waste
and
TRU
waste
that
have
been
characterized
in
accordance
with
the
WIPP­
WAP
and
meet
the
treatment,
storage,
and
disposal
facility
(
TSDF)
waste
acceptance
criteria
as
presented
in
permit
conditions
II.
C.
3.
a
through
II.
C.
3.
k
of
the
WIPP
Hazardous
Waste
Facility
Permit
will
be
accepted
at
the
WIPP
facility
for
disposal
in
the
permitted
underground
hazardous
waste
disposal
unit.

Before
disposal,
HNF­
2599,
addressing
all
the
applicable
requirements
specified
in
the
WIPPWAP
shall
be
implemented.
In
accordance
with
attachment
B5
of
the
WIPP­
WAP,
HNF­
2599
will
include
the
qualitative
or
quantitative
criteria
for
making
a
hazardous
waste
determination.
HNF­
2599
will
be
reviewed
and
approved
by
the
CBFO.

3.1.3.2
Compliance
and
Verification
CH
waste
sent
to
WIPP
will
be
certified
in
accordance
with
HNF­
2599
and
HNF­
2600
requirements.
HNF­
2599
implements
the
applicable
requirements
in
the
WIPP­
WAP
for
mixed
and
non­
mixed
TRU
waste
characterization
activities
and
includes
the
qualitative
and
quantitative
criteria
for
making
hazardous
waste
determinations.
HNF­
2599
is
approved
by
CBFO.

3.1.4
EPA
Requirements
3.1.4.1
EPA
Compliance
Certification
Decision
Title
40
CFR
Part
194.24(
c)
required
that
the
DOE
specifies
the
limiting
values
for
waste
components
for
acceptance
to
WIPP.
The
EPA's
Compliance
Certification
Decision
identified
the
repository
limits
for
several
waste
components,
including
free
water
and
metals,
and
cellulose,
plastic,
and
rubber
(
CPR).
Although
the
Compliance
Certification
Decision
did
not
specify
limiting
values
for
the
activities
and
masses
of
specific
radionuclides,
it
did
identify
the
HNF­
2600,
REV
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HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
listed
values
for
a
number
of
radionuclides
that
are
considered
in
the
performance
assessment.
To
demonstrate
that
the
cumulative
total
activities
of
the
specified
radionuclides
(
241Am,
238Pu,
239Pu,
240Pu,
242Pu,
233U,
234U,
238U,
90Sr,
and
137Cs)
are
consistent
with
the
levels
used
for
the
performance
assessment
and
the
compliance
certification
decision,
reporting
and
tracking
of
the
specified
radionuclides
(
241Am,
238Pu,
239Pu,
240Pu,
242Pu,
233U,
234U,
238U,
90Sr,
and
137Cs)
are
necessary,
as
required
by
the
Compliance
Certification
Decision.
TRU
waste
payload
containers
shall
contain
more
than
100
nanocuries
per
gram
of
waste
(
nCi/
g)
of
alpha­
emitting
TRU
isotopes
with
half­
lives
greater
than
20
years.

The
WIPP
limit
for
free
water
is
a
maximum
of
1684
m3
and
is
met
by
the
residual
liquid
criterion.

The
limits
for
metals
are
a
minimum
of
2
×
107
kg
for
ferrous
metals
and
2
×
103
kg
for
nonferrous
metals.
These
limits
will
be
met
in
the
total
repository
inventory
by
the
metals
that
constitute
the
payload
containers
alone;
thus,
WIPP
tracks
the
number
and
type
of
payload
containers
emplaced
in
the
repository
as
reported
in
the
WWIS
by
Hanford.

The
WIPP
limit
for
CPR
is
a
maximum
of
2
×
107
kg.
The
CPR
weights
must
be
estimated
and
reported
in
the
WWIS
on
a
payload
container
basis.

Ten
specific
radionuclides
must
be
quantified
and
reported
for
masses
and
activity
for
the
purpose
of
tracking
the
total
radionuclide
inventory
at
WIPP.
The
presence
or
absence
of
these
specific
radionuclides
is
determined
from
AK,
radioassay,
or
both
in
accordance
with
Appendix
E.
The
results
of
this
determination
are
reported
in
the
WWIS
on
a
payload
container
basis.

3.1.4.2
Compliance
and
Verification
CH
waste
sent
to
WIPP
will
be
certified
in
accordance
with
HNF­
2599
and
this
Certification
Plan.
Subsection
3.3.1
and
Appendix
E
of
this
Certification
Plan
outline
the
specific
requirements
and
compliance
activities
related
to
radiological
properties
performed
consistent
with
the
CH­
WAC.
HNF­
2599
identifies
compliance
activities
meeting
the
other
EPA
compliance
certification
requirements
(
e.
g.,
residual
liquids,
metals,
CPR).

3.1.4.3
EPA
Approval
for
PCB
Disposal
TRU
and
TRU­
mixed
wastes
containing
PCBs,
including
PCB
remediation
waste,
PCB
bulk
product
waste,
etc.
may
be
disposed
of
at
the
WIPP.
Applicable
waste
acceptance
criteria
are
addressed
in
subsections
3.2.5
(
Container
Identification/
Labeling),
3.4.1
(
Residual
Liquids),
and
3.5.6
(
Polychlorinated
Biphenyls)
of
the
CH­
WAC.

3.1.4.4
Compliance
and
Verification
CH
waste
sent
to
WIPP
will
be
certified
in
accordance
with
HNF­
2599
and
this
Certification
Plan.
Subsections
3.2.5
(
Container
Identification/
Labeling),
3.4.1
(
Residual
Liquids),
3.5.6
(
Polychlorinated
Biphenyls)
outline
the
specific
requirements
and
compliance
activities
related
to
PCBs
consistent
with
the
CH­
WAC.
HNF­
2600,
REV
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HANFORD
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3.1.5
Land
Withdrawal
Act
Requirements
3.1.5.1
Requirements
The
term
"
WIPP"
means
the
Waste
Isolation
Pilot
Plant
project
authorized
under
Section
213
of
the
Department
of
Energy
National
Security
and
Military
Applications
of
Nuclear
Energy
Authorization
Act
of
1980
(
Pub.
L.
96­
164;
93
Stat.
1259­
1265)
to
demonstrate
the
safe
disposal
of
radioactive
waste
materials
generated
by
Atomic
Energy
defense
activities.
Hence,
by
law,
WIPP
can
accept
only
radioactive
waste
generated
by
Atomic
Energy
defense
activities
of
the
United
States.

The
DOE
and
its
predecessor
agencies
were
engaged
in
a
broad
range
of
activities
that
fall
under
the
heading
of
Atomic
Energy
defense
activities.
A
TRU
waste
is
eligible
for
disposal
at
WIPP
if
it
has
been
generated
in
whole
or
in
part
by
one
or
more
of
the
following
functions:

 
Naval
reactors
development
 
Weapons
activities,
including
defense
inertial
confinement
fusion
 
Verification
and
control
technology
 
Defense
nuclear
materials
productions
 
Defense
nuclear
waste
and
materials
by­
products
management
 
Defense
nuclear
materials
security
and
safeguards
and
security
investigations
 
Defense
research
and
development.

Using
AK,
DOE
sites
must
determine
that
each
waste
stream
to
be
disposed
of
at
WIPP
is
"
defense"
TRU
waste.

High­
level
radioactive
waste
or
spent
nuclear
fuel
shall
neither
be
transported,
emplaced,
nor
disposed
of
at
WIPP.
Also,
no
TRU
waste
may
be
transported
by
or
for
the
DOE
to
or
from
WIPP,
except
in
packages
(
1)
the
design
of
which
has
been
certified
by
the
NRC,
and
(
2)
that
have
been
determined
by
the
NRC
to
satisfy
its
QA
requirements.

3.1.5.2
Compliance
and
Verification
Only
CH
TRU
defense
waste
characterized
in
accordance
with
the
WIPP­
WAP,
CH­
WAC,
and
consistent
with
HNF­
2599
and
this
certification
plan
will
be
transported
to
WIPP
for
disposal.
Each
TRU
waste
stream
is
evaluated
to
determine
whether
the
waste
is
designated
defense.
This
determination
is
documented
in
the
AK
documentation
as
required
by
WMP­
400,
Section
7.1.9,
"
Acceptable
Knowledge
Documentation
Management."

3.1.6
Energy
and
Water
Development
Appropriations
Act
(
Title
III,
General
Provisions)

3.1.6.1
Requirements
The
first
sentence
of
the
following
language
has
appeared
in
various
sections
of
Title
III
of
the
Energy
and
Water
Development
Appropriations
Act
for
every
fiscal
year
since
1999.
HNF­
2600,
REV
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HANFORD
SITE
TRANSURANIC
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CERTIFICATION
PLAN
None
of
the
funds
in
this
Act
may
be
used
to
dispose
of
transuranic
waste
in
the
Waste
Isolation
Pilot
Project
Plant
which
contains
concentrations
of
plutonium
in
excess
of
20
percent
by
weight
for
the
aggregate
of
any
material
category
on
the
date
of
enactment,
or
is
generated
after
such
date.
For
the
purposes
of
this
section,
the
material
categories
of
transuranic
waste
at
the
Rocky
Flats
Environmental
Technology
Site
include:
(
1)
ash
residues;
(
2)
salt
residues;
(
3)
wet
residues,
(
4)
direct
package
residues;
and
(
5)
scrub
alloy
as
referenced
in
the
"
Final
Environmental
Impact
Statement
on
Management
of
Certain
Plutonium
Residues
and
Scrub
Alloy
Stored
at
the
Rocky
Flat
Environmental
Technology
Site."

Note:
The
first
sentence
of
the
language
above
is
the
only
portion
of
the
section
that
applies
to
transuranic
(
TRU)
waste
generator/
storage
sites
other
than
Rocky
Flats.

The
CBFO
strongly
encourages
the
TRU
waste
generator/
storage
sites
to
work
with
DOE
Headquarters
General
Counsel
to
obtain
a
determination
of
compliance
with
this
language
for
high
plutonium
content
material/
waste
that
is
ultimately
planned
for
disposal
at
the
WIPP
prior
to
initiating
TRU
waste
characterization
activities.
Evidence
used
to
support
a
determination
of
compliance
as
well
as
the
compliance
decision
must
be
included
in
the
waste
stream
AK
documentation.
This
information
must
also
be
included
in
the
AK
summary
accompanying
waste
stream
profile
forms
submitted
to
the
CBFO.

3.1.6.2
Compliance
and
Verification
The
Hanford
TRU
Program
will
work
with
DOE
Headquarters
General
Counsel
to
obtain
a
determination
of
compliance
with
this
language
for
high
plutonium
content
material/
waste
that
is
ultimately
planned
for
disposal
at
the
WIPP,
during
the
waste
stream
development
process.
Evidence
used
to
support
a
determination
of
compliance
as
well
as
the
compliance
decision
will
be
included
in
the
waste
stream
AK
documentation
consistent
with
WMP­
400,
Section
7.1.9,
Acceptable
Knowledge
Documentation
Management.
This
information
will
be
included
in
the
AK
summary
accompanying
waste
stream
profile
forms
submitted
to
the
CBFO.

3.2
CONTAINER
PROPERTIES
CRITERIA
AND
REQUIREMENTS
3.2.1
Payload
Container
Description
3.2.1.1
Requirements
Each
CH­
TRU
Payload
Container
shall
be
assigned
to
a
payload
shipping
category.
Authorized
payload
container
types
include
the
following:

 
55­
gallon
drums
 
55­
gallon
drums
(
containing
a
pipe
overpack)
 
85­
gallon
drums
(
the
term
"
85­
gallon
drum"
includes
75­
to
88­
gallon
drums)
 
standard
waste
boxes
(
SWBs,
either
direct
loaded,
containing
up
to
four
55­
gallon
drums,
or
containing
one
bin)
 
ten
drum
overpacks
(
TDOPs,
either
direct
loaded,
containing
up
to
ten
55­
gallon
drums,
up
to
six
85­
gallon
drums,
or
one
SWB)
HNF­
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HANFORD
SITE
TRANSURANIC
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CERTIFICATION
PLAN
Payload
containers
shall
meet
U.
S.
Department
of
Transportation
(
DOT)
Specification
7A,
Type
A
packaging
requirements.
Payload
containers
must
be
made
of
steel
and
be
in
good
and
unimpaired
condition
prior
to
shipment
from
the
generator/
storage
sites.
To
demonstrate
compliance
with
the
requirement
that
payload
containers
be
in
good
and
unimpaired
condition,
the
exterior
of
all
payload
containers
shall
undergo
100%
visual
examination
prior
to
loading
into
a
TRUPACT­
II.
The
results
of
this
visual
examination
shall
be
documented
using
the
payload
container
integrity
checklist
in
Appendix
D
of
the
CH­
WAC.
A
payload
container
in
good
and
unimpaired
condition
consists
of
the
following:

1.
Does
not
have
significant
rusting,

2.
Is
of
sound
structural
integrity,
and
3.
Does
not
leak.

Significant
rusting
is
a
readily
observable
loss
of
metal
due
to
oxidation
(
e.
g.,
flaking,
bubbling,
or
pitting)
that
causes
degradation
of
the
payload
container's
structural
integrity.
Rusting
that
causes
discoloration
of
the
payload
container
surface
or
consists
of
minor
flaking
is
not
considered
significant.
A
payload
container
is
not
of
sound
structural
integrity
if
it
has
breaches
or
significant
denting/
deformation.
Breaching
is
defined
as
a
penetration
in
the
payload
container
that
exposes
the
internals
of
the
container.
Significant
denting/
deformation
is
defined
as
damage
to
the
payload
container
that
results
in
creasing,
cracking,
or
gouging
of
the
metal,
or
damage
that
affects
payload
container
closure.
Dents
or
deformations
that
do
not
result
in
creasing,
cracking,
or
gouging
or
affect
payload
container
closure
are
not
considered
significant.
Generator
sites
will
report
to
the
WWIS
the
number
and
types
of
payload
containers
planned
for
shipment
to
the
WIPP.

3.2.1.2
Compliance
and
Verification
See
subsection
4.3.1.2.

3.2.2
Container
Weight
and
Center
of
Gravity
3.2.2.1
Requirements
Each
payload
container,
payload
assembly,
and
loaded
TRUPACT­
II
shall
comply
with
the
weight
limits
shown
in
table
3.2­
1
of
this
Certification
Plan.
Weight
calculations
for
the
payload
assembly
must
include
the
measurement
error
in
accordance
with
the
CH­
TRAMPAC.
For
TRUPACT­
II
payloads,
the
total
weight
of
payload
container(
s)
in
the
top
layer
of
the
payload
assembly
shall
be
less
than
or
equal
to
the
total
weight
of
the
payload
container(
s)
in
the
bottom
layer
of
the
payload
assembly.
In
the
case
of
drums
over
packed
in
a
TDOP,
the
total
weight
of
the
top
layer
of
drums
shall
be
less
than
or
equal
to
the
total
weight
of
the
bottom
layer
of
drums.
Calibrations
of
the
scales
used
to
make
these
weight
determinations
shall
be
in
accordance
with
the
National
Institute
of
Standards
and
Technology
(
NIST)
Handbook
44
or
an
equivalent
standard.
HNF­
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HANFORD
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Table
3.2­
1
Weight
Limits
Loaded
Units
Maximum
Gross
Weight
(
lbs)
Payload
Containers
55­
gallon
drum
 
1000
55­
gallon
drum
containing
a
six­
inch­
diameter
pipe
component
(
i.
e.,
a
standard
pipe
overpack)
 
328
55­
Gallon
drum
containing
a
twelve­
inchdiameter
pipe
component
(
i.
e.,
a
standard
pipe
overpack)
 
547
55­
gallon
drum
containing
a
neutron
shielded
six­
inch­
diameter
pipe
component
(
i.
e.,
an
S100
pipe
overpack)
 
550
55­
gallon
drum
containing
a
gamma
shielded
twelve­
inch­
diameter
pipe
component
(
i.
e.,
an
S200
pipe
overpack)
 
547
85­
gallon­
drum
 
1,000
SWB
 
4,000
TDOP
 
6,700
Payload
Assemblies1
TRUPACT­
II
payload
assemblies
including
fourteen
55­
gallon
drums,
fourteen
pipe
overpacks
(
standard,
S100,
or
S200),
eight
85­
gallon
drums,
two
SWBs,
or
one
TDOP
 
7,265
Packages/
Truck
TRUPACT­
II
 
19,
250
Truck
(
tractor/
trailer)
 
80,000
1Refer
to
section
3.2.3
of
this
document
for
an
explanation
of
how
payload
assemblies
are
built.

3.2.2.2
Compliance
and
Verification
See
subsection
4.3.3.2.

3.2.3
Assembly
Configurations
3.2.3.1
Requirements
Payload
container
assembly
configurations
authorized
for
shipment
in
the
TRUPACT­
II
shall
be
in
accordance
with
table
3.2­
2
below.
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WASTE
CERTIFICATION
PLAN
Table
3.2­
2
TRUPACT­
II
Payload
Assembly
Configurations
Number
of
Payload
Containers
in
Assembly1
Payload
Container
Configuration
14
55­
gal.
drums
14
55­
gal.
drums
configured
as,
standard
pipe
overpacks2
14
55­
gallon
drums
configured
as
S100
pipe
overpacks
14
55­
gallon
drums
configured
as
S200
pipe
overpacks3
8
85­
gallon
drums4
2
SWBs
1
TDOP
1Payloads
shall
be
comprised
of
a
single
payload
container
type.
In
the
case
of
standard
pipe
overpacks
assembled
in
a
payload
with
55­
gallon
drums,
however,
the
standard
pipe
overpacks
are
considered
55­
gallon
drums
and
are
subject
to
the
applicable
limits.
2Standard
pipe
overpacks
must
be
assembled
into
seven­
packs
of
six­
inch
standard
pipe
overpacks
only
or
twelve­
inch
standard
pipe
overpacks
only.
3A
mixture
of
S200­
A
and
S­
200­
B
pipe
overpacks
may
be
assembled
into
a
single
payload.
4Only
the
short
85­
gallon
drum
is
authorized
for
transport
within
the
TRUPACT­
II
as
a
payload
container.
A
TRUPACT­
II
payload
may
contain
assembles
of
payload
containers
belonging
to
the
same
shipping
category,
equivalent
shipping
categories
or
different
(
nonequivalent)
shipping
categories.

3.2.3.2
Compliance
and
Verification
See
subsection
4.3.1.2.

3.2.4
Removable
Surface
Contamination
(
Payload
Containers)

3.2.4.1
Requirements
The
removable
surface
contamination
for
each
CH
TRU
waste
payload
container
or
payload
container
assembly
must
be
measured
and
documented
before
shipment.
Removable
surface
contamination
on
CH
TRU
waste
payload
containers,
payload
assemblies,
and
packagings
shall
not
be
greater
than
20
disintegrations
per
minute
(
dpm)
per
100
cm2
for
alpha­
emitting
radionuclides
or
200
dpm
per
100
cm2
for
beta­
gamma
emitting
radionuclides.
Fixing
surface
contamination
to
meet
the
above
criteria
is
not
permitted.
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HANFORD
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CERTIFICATION
PLAN
3.2.4.2
Compliance
and
Verification
A
Hanford
site
radiological
control
technician
(
RCT)
surveys
TRU
waste
containers
and
container
assemblies
for
removable
surface
contamination
before
the
containers
are
loaded
for
shipment.
The
RCT
assesses
removable
contamination
and
documents
the
results
in
accordance
with
WRP1­
OP­
1225,
"
Radiological
Support
of
TRUPACT­
II
Shipping
and
Receiving."
If
the
RCT
determines
that
removable
contamination
exceeds
20
dpm
per
100
cm2
for
alpha­
emitting
radionuclides
or
200
dpm
per
100
cm2
for
beta­
gamma
emitting
radionuclides,
project
personnel
determine
whether
surface
contamination
can
be
removed
to
meet
established
limits.
If
compliance
with
removable
surface
contamination
limits
cannot
be
achieved,
project
personnel
segregate
and
disposition
noncompliant
container(
s)
in
accordance
with
nonconformance
and
corrective
action
procedures.
The
survey
results
are
added
to
the
container
data
package
as
described
in
WMP­
400,
Section
7.1.8,
"
Transuranic
Waste
Certification."
The
TCO
and
WCO
confirm
removable
surface
contamination
survey
results
in
accordance
with
WMP­
400,
Sections
2.1.5,
TRU
Waste
Transportation
Certification
and
Logistics
and
7.1.8
respectively.

3.2.5
Container
Identification/
Labeling
3.2.5.1
Requirements
Each
CH
TRU
waste
payload
container
shipped
in
a
TRUPACT­
II
shall
be
uniquely
identified
by
means
of
labels
permanently
attached
in
conspicuous
locations.
The
labels
shall
contain
a
unique
container
identification
number
(
CIN)
consisting
of
site
and
container
information.
The
CIN
shall
be
in
medium­
to
low­
density
Code
39
bar
code
symbology
(
per
ANSI/
AIM
BC1­
1995)
in
characters
at
least
1­
inch
high,
and
alphanumeric
characters
at
least
0.5­
inches
high.
The
bar
code
identification
labels
shall
be
placed
at
three
locations
about
120
degrees
apart
so
that
at
least
one
label
is
clearly
visible
when
drums
are
assembled
into
a
payload
(
e.
g.,
a
label
must
be
visible
after
slip­
sheets
and
wrapping
are
applied).
Labels
are
required
on
the
flat
sides
of
SWBs.
For
TDOPs,
a
minimum
of
one
bar
code
is
required.
Containers
shall
be
marked
in
accordance
with
10
CFR
Part
835
and/
or
40
CFR
§
262.32,
as
applicable.
See
subsection
3.2.6
of
this
Certification
Plan
for
dunnage
container
labeling
requirements.

Payload
containers
shall
be
marked
"
Caution
Radioactive
Material"
with
the
yellow
and
magenta
label,
consistent
with
10
CFR
Part
835.
Those
payload
containers
that
are
RCRA
regulated
will
have
the
hazardous
waste
label
affixed
in
accordance
with
40
CFR
§
262.32.
For
TRU
and
TRU­
mixed
wastes
containing
PCBs,
the
payload
containers
shall
be
marked
in
accordance
with
40
CFR
§
761.40.
Additionally,
DOT
Type
B
packages
(
i.
e.,
the
TRUPACT­
II)
containing
PCBs
must
be
properly
marked
in
accordance
with
40
CFR
§
761.40.

If
an
empty
55­
or
85­
gallon,
drum
is
used
as
dunnage
to
complete
a
payload
configuration,
the
dunnage
container
shall
be
labeled
with
the
following
information:

 
Unique
payload
container
identification
number
 
"
EMPTY"
or
"
DUNNAGE"
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HANFORD
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TRANSURANIC
WASTE
CERTIFICATION
PLAN
If
a
seven­
pack
of
only
dunnage
55­
gallon
drums,
a
four­
pack
of
only
dunnage
85­
gallon
drums,
or
a
dunnage
SWB
is
used
in
the
TRUPACT­
II,
the
containers(
s)
shall
be
labeled
only
"
EMPTY"
or
"
DUNNAGE"
and
the
unique
container
identification
number
label
is
not
required
for
these
containers.

3.2.5.2
Compliance
and
Verification
Waste
containers
currently
in
the
Central
Waste
Complex
(
CWC)
have
a
permanent
bar
code
label
containing
a
unique
identification
number.
Generators
procure
waste
containers
with
bar
code
labels
affixed
in
accordance
with
the
Hanford
site's
container
management
program.
Before
loading
containers
in
the
TRUPACT­
II,
WIPP
bar
code
labels
are
added
in
three
locations
to
each
drum
such
that
each
bar
code
label
is
approximately
120
degrees
apart
around
the
drum.
For
SWBs,
labels
are
required
on
flat
sides.
One
label
is
required
per
TDOP.

After
verifying
all
payload
parameters,
project
personnel
mark
each
container
with
the
appropriate
site
and
container
information).
The
TCO
verifies
compliance
with
container
marking
requirements
by
visually
inspecting
all
TRU
waste
containers
and
their
labels
and
comparing
them
to
the
container
data
package
before
shipment,
in
accordance
with
WMP­
400,
Section
2.1.5.
The
TCO
verifies
the
container
marking
as
described
in
WMP­
400,
Section
2.1.5.

3.2.6
Dunnage
3.2.6.1
Requirements
If
too
few
loaded
payload
containers
meeting
all
payload
container
and
transportation
requirements
are
available,
dunnage
must
complete
one
of
the
configurations
specified
in
table
3.2­
2.
Empty
55­
gallon
drums,
85­
gallon
drums,
or
an
empty
SWB
may
be
used
as
dunnage,
as
specified
in
section
3.2.5
of
the
CH­
WAC
and
section
2.9
of
the
CH­
TRAMPAC,
with
the
exception
that
dunnage
containers
shall
have
at
least
one
open
vent
port
(
i.
e.,
not
filtered
or
plugged).
If
an
empty
55­
or
85­
gallon,
drum
is
used
as
dunnage
to
complete
a
payload
configuration
in
a
shipment
to
WIPP,
the
dunnage
container
shall
contain
a
unique
payload
container
identification
number,
be
labeled
"
EMPTY"
or
"
DUNNAGE"
and
have
a
container
marking
in
accordance
with
subsection
3.2.5
of
this
certification
plan,
as
appropriate.
.
If
a
seven­
pack
of
only
dunnage
55­
gallon
drums,
a
four­
pack
of
only
dunnage
85­
gallon
drums,
or
a
dunnage
SWB
is
used
in
the
TRUPACT­
II,
the
container(
s)
shall
be
labeled
only
"
empty"
or
"
dunnage"
and
the
unique
identification
number
label
is
not
required
for
these
containers.
The
use
of
dunnage
should
be
minimized.
The
use
of
dunnage
is
reviewed
and
approved
concurrently
with
the
review
and
approval
of
shipment
assemblies
by
the
WWIS
data
administrator
on
a
case­
by­
case
basis.

3.2.6.2
Compliance
and
Verification
See
subsection
4.3.2.2.
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HANFORD
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PLAN
3.2.7
Filter
Vents
3.2.7.1
Requirements
Payload
containers
that
have
been
stored
in
an
unvented
condition
(
i.
e.,
no
filter
and/
or
unpunctured
liner)
shall
be
aspirated
for
a
specific
length
of
time
as
described
in
the
CH­
TRAMPAC
to
ensure
equilibration
of
any
gases
that
may
have
accumulated
in
the
closed
payload
container.

Each
payload
container
shall
have
one
or
more
filter
vents
that
meet
the
specifications
of
Section
2.5
of
the
CH­
TRAMPAC
and
Attachment
B1
of
the
WIPP
Hazardous
Waste
Facility
Permit.
The
model
number
of
each
filter
vent
or
combination
of
filter
vents
installed
on
a
payload
container
shall
be
reported
to
the
WWIS.
A
listing
of
available
CBFO
filter
vent
models
is
provided
on
the
CBFO
web
page
(
http://
www.
wipp.
ws/
transport.
htm).
This
Internet
link
is
provided
for
informational
purposes
only
and
may
change.

3.2.7.2
Compliance
and
Verification
See
subsection
4.3.5.2.

3.3
RADIOLOGICAL
PROPERTIES
CRITERIA
AND
REQUIREMENTS
3.3.1
Radiological
Properties
With
respect
to
the
required
radiological
properties
identified
within
this
section,
they
can
be
divided
into
two
distinct
groups.

The
first
group
includes
the
activities
and
masses
of
the
ten
WIPP­
tracked
radionuclides
(
241Am,
238Pu,
239Pu,
240Pu,
242Pu,
233U,
234U,
238U,
90Sr,
and
137Cs)
and
the
TRU
alpha
activity
concentrations
(
i.
e.,
>
100
nCi/
g
of
alpha­
emitting
TRU
isotopes
with
half
lives
greater
than
20
years)
of
the
waste.
This
set
of
radiological
properties
is
regulated
by
the
EPA
in
accordance
with
40
CFR
Parts
191
and
194.
Estimates
of
their
activities
and
masses
shall
be
derived
from
a
system
of
controls
certified
by
CBFO
that
includes
AK,
computations,
measurements,
sampling,
etc.
Appendix
A
of
the
CH­
WAC
provides
the
methods
and
requirements
by
which
to
characterize
the
radiological
composition
of
the
CH­
TRU
waste
utilizing
radioassay
techniques.

The
second
group
includes
the
remaining
radionuclides
contributing
to
the
239Pu
fissile
gram
equivalent
(
FGE),
the
239Pu
equivalent
curies
(
PE­
Ci),
and
the
decay
heat
of
the
payload
container.
This
set
of
radiological
data
is
regulated
both
by
the
NRC
as
specified
in
the
CH­
TRAMPAC
and
the
CBFO
as
required
by
the
WIPP
Technical
Safety
Requirements.
PE­
Ci
quantities
shall
be
calculated
for
each
payload
container
in
accordance
with
Appendix
B
of
the
CH­
WAC.
Any
CH­
TRAMPAC
compliant
method
may
be
used
to
quantify
the
remaining
radiological
properties.
However,
the
resulting
data
(
e.
g.,
AK
from
Safeguards
and
Security
data),
the
source/
method
from
which
the
data
was
generated,
and
the
basis
for
the
reliability
of
the
data
shall
be
submitted
to
and
approved
by
CBFO
prior
to
use.
HNF­
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HANFORD
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WASTE
CERTIFICATION
PLAN
3.3.2
Radionuclide
Composition
3.3.2.1
Requirements
The
activities
and
masses
of
241Am,
238Pu,
239Pu,
240Pu,
242Pu,
233U,
234U,
238U,
90Sr,
and
137Cs
shall
be
established
on
a
payload
container
basis
for
purposes
of
tracking
their
contributions
to
the
total
WIPP
radionuclide
inventory.
The
estimated
activities
and
masses,
including
their
associated
total
measurement
uncertainties
(
TMU)
expressed
in
terms
of
one
standard
deviation,
for
these
ten
radionuclides
shall
be
reported
to
the
WWIS
on
a
payload
container
basis.
For
any
of
these
ten
radionuclides
whose
presence
can
be
substantiated
from
AK,
direct
measurement,
computations,
or
a
combination
thereof,
and
whose
measured
data
are
determined
to
be
below
the
lower
limit
of
detection
(
LLD)
for
that
radionuclide,
the
site
shall
report
the
character
string
"<
LLD"
to
the
WWIS
for
the
activity
and
mass
of
that
radionuclide;
otherwise
a
value
of
zero
shall
be
reported.
Quantitative
estimates
for
LLD
shall
not
be
used
when
calculating
related
radiological
properties
of
the
waste
such
as
TRU
alpha
activity
concentration,
239Pu
fissile
gram
equivalent,
decay
heat,
etc.
Section
A.
3,
item
1,
of
the
CH­
WAC
has
information
pertaining
to
the
development
and
application
of
LLD.

In
addition
to
the
ten
WIPP­
tracked
radionuclides,
the
activity
of
other
radionuclides
contributing
to
the
239Pu
fissile
gram
equivalent
(
FGE),
the
239Pu
equivalent
curies
(
PE­
Ci),
or
decay
heat
of
the
payload
container
that
are
used
to
determine
(
e.
g.,
correlate
or
scale)
the
activity
of
one
of
the
ten
WIPP­
tracked
isotopes
or
otherwise
contributes
to
at
least
95
percent
of
the
total
radiological
hazard
must
also
be
determined
in
order
to
meet
the
CH­
TRAMPAC,
DOT,
and/
or
NRC
requirements.
PE­
Ci
shall
be
determined
in
accordance
with
Appendix
E
of
this
Certification
Plan,
and
any
CH­
TRAMPAC­
compliant
method
may
be
used
to
determine
the
other
radiological
properties.
Appendix
E
of
this
Certification
Plan
provides
radioassay
requirements
by
which
to
characterize
the
waste.
However,
the
resulting
data
(
e.
g.,
AK
from
Safeguards
and
Security
data),
the
source/
method
from
which
the
data
was
generated,
and
the
basis
for
the
reliability
of
the
data
shall
be
submitted
to
and
approved
by
CBFO
before
use.
These
other
isotopes
shall
be
reported
on
the
TRUPACT­
II
bill
of
lading
(
BOL)
or
manifest
in
accordance
with
49
CFR
§
172.203
and
49
CFR
§
173.433.
The
activities
and
masses
of
these
other
radioisotopes
shall
also
be
reported
to
the
WWIS
along
with
their
associated
TMU,
expressed
in
terms
of
one
standard
deviation
for
each
waste
container.

3.3.2.2
Compliance
and
Verification
Nondestructive
assay
(
NDA)
personnel
perform
measurements
of
each
TRU
waste
container
using
calorimetry,
gamma
energy
assay
(
GEA),
imaging
passive/
active
neutron
(
IPAN),
or
passive
neutron
(
e.
g.,
SuperHENC)
systems
to
determine
the
radioactive
material
composition
and
quantify
radionuclide
masses.
The
requirements
for
NDA
are
presented
in
Appendix
E
of
this
certification
plan,
and
the
equipment
and
procedures
are
approved
by
CBFO.

NDA
personnel
at
the
Waste
Receiving
and
Processing
(
WRAP)
facility
follow
NDA
procedures
described
in
WRP1­
OP­
0906,
"
Gamma
Energy
Assay
Operations,"
WRP1­
OP­
0905,
"
Imaging
Passive/
Active
Neutron
Assay
Operations,"
WRP1­
OP­
0907,
"
Gamma
Energy
Assay
Operations
Using
NDA2000,"
or
TRU­
OP­
002,
"
Operation
of
the
SuperHENC
Assay
Systems."
NDA
HNF­
2600,
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55
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HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
personnel
at
WRAP
quantify
radionuclide
values
in
accordance
with
WMP­
350,
Waste
Receiving
and
Processing
Facility,
Section
2.2,
"
Calculation
of
Assay
Results."
NDA
personnel
at
WRAP
use
acceptable
knowledge
(
AK)
data
and
assay
measurements
and
calculations
to
establish
an
isotopic
profile
of
each
waste
container,
which
is
reported
in
batch
data
reports
in
accordance
with
WMP­
350,
Section
2.3,
"
Data
Management,"
and
Section
2.8,
"
WRAP
NDA
Measurement
Control
Program."

NDA
personnel
at
the
Plutonium
Finishing
Plant
(
PFP)
follow
one
of
two
NDA
procedures
listed
below:

 
ZA­
948­
392,
"
NDA
Using
NDA
2000"
or
 
ZA­
948­
393,
"
NDA
Using
the
Room
172
ANTECH
Calorimeters"

NDA
personnel
at
PFP
calibrate
the
various
assay
systems
in
accordance
with
one
of
the
two
procedures
listed
below:

 
ZA­
400­
303,
"
Energy
and
Efficiency
Setup
and
Baseline
Determination
Using
NDA
2000"
or
 
ZA­
400­
304,
"
ANTECH
Calorimeter
Calibration"

NDA
personnel
at
PFP
quantitate
radionuclide
values
in
accordance
with
ZA­
400­
302,
"
Calculation
of
Assay
Results."
NDA
personnel
at
PFP
use
AK
data
and
assay
measurements
and
calculations
to
create
an
isotopic
profile
of
each
waste
container,
which
is
reported
in
batch
data
reports
in
accordance
with
FSP­
PFP­
5­
8,
Plutonium
Finishing
Plant
Administration,
Section
16.2,
"
Data
Management."

The
WCO
reports
NDA
data
to
WWIS
and
appropriate
container
certifications
in
accordance
with
WMP­
400,
Sections
7.1.5
and
7.1.8.
The
TCO
reports
NDA
data
to
shipping
documents
in
accordance
with
WMP­
400,
Section2.1.5.

3.3.3
Fissile
Material
Quantity
(
239Pu
Fissile
Gram
Equivalents
[
FGE])

3.3.3.1
Requirements
For
each
payload
container
and
loaded
TRUPACT­
II,
the
sum
of
239Pu
FGE
plus
two
times
its
associated
TMU,
expressed
in
terms
of
one
standard
deviation,
shall
comply
with
the
limits
in
either
table
3.3­
1
or
table
3.3­
2
as
applicable.
The
values
calculated
for
239Pu
FGE
and
its
associated
TMU
(
expressed
in
terms
of
one
standard
deviation)
shall
be
reported
to
the
WWIS
for
each
payload
container.
HNF­
2600,
REV
15
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56
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2005
HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
Table
3.3­
1
239Pu
FGE
Limits
for
Payload
Containers
Payload
Containers
Beryllium
Mass
Limit1
239Pu
FGE
Limit2
Applicable
to
Non­
Machine­
Compacted
Waste
55­
(
excluding
pipe
overpacks)
and
85­
gallon
drums
 
1%
by
weight
of
the
waste
 
200
55­
gallon
drum
configured
as
a
pipe
overpack
(
i.
e.,
a
standard
S100
or
S200
pipe
overpack
 
5
kg
 
200
SWB
 
1%
by
weight
of
the
waste
up
to
18.14
kg
and
is
particulate3
 
325
TDOP
 
1%
by
weight
of
the
waste
up
to
18.14
kg
and
is
particulate3
 
325
55­
(
excluding
pipe
overpacks)
and
85­
gallon
drums
>
1%
by
weight
of
the
waste
up
to
100
kg
 
100
SWB
>
1%
by
weight
of
the
waste
up
to
18.14
kg
and
is
particulate3
 
100
TDOP
>
1%
by
weight
of
the
waste
up
to
18.14
kg
and
is
particulate3
 
100
Machine­
Compacted
Waste
Not
Implemented
at
Hanford
1Beryllium
includes
both
the
metal
(
Be)
and
its
oxide
(
BeO).
2The
FGE
limit
given
applies
to
the
payload
container
regardless
of
240Pu
content
in
the
package.
3Particulate
beryllium
includes
fines
or
shavings.
HNF­
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HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
Table
3.3­
2
239Pu
FGE
Limits
for
Packages
Payload
Packages
239Pu
FGE
Limit
(
No
Credit
for
240Pu
Poisoning)
239Pu
FGE
Limit
(
Credit
for
240Pu
Poisoning1)

Applicable
to
Beryllium2
Mass
 
1%
by
Weight
of
the
Waste
and
Non­
Machine­
Compacted
Waste
5
g
240Pu
 
340
15
g
240Pu
 
360
TRUPACT­
II
(
containing
either
14
55­
gallon
drums,
8
85­
gallon
drums,
2
SWBs,
or
1
TDOP3)
 
325
25
g
240Pu
 
380
TRUPACT­
II
(
containing
either
14
standard
pipe
overpacks,
14
S100
pipe
overpacks,
or
14
S200
pipe
overpacks)
 
2800
Unauthorized
HalfPACT
(
Not
implemented
at
Hanford)
Applicable
to
Beryllium2
Mass
>
1%
by
Weight
of
the
Waste
and
Non­
Machine­
Compacted
Waste
TRUPACT­
II
(
containing
either
14
55­
gallon
drums,
8
85­
gallon
drums,
2
SWBs,
or
1
TDOP)
 
100
Unauthorized
HalfPACT
(
Not
implemented
at
Hanford)
Applicable
to
Beryllium2
Mass
 
1%
by
Weight
of
the
Waste
and
Machine­
Compacted
Waste4
Not
Implemented
at
Hanford
Applicable
to
Beryllium2
Mass
>
1%
by
Weight
of
the
Waste
and
Machine­
Compacted
Waste4
Unauthorized
1The
numbers
0,
5,
15,
and
25
represent
the
minimum
240Pu
content
of
the
payload
expressed
in
grams
that
must
be
exceeded
to
take
credit
for
the
higher
FGE
loading
limit.
The
minimum
240Pu
content
for
the
payload
shall
be
determined
after
subtraction
of
two
times
the
error.
2Beryllium
includes
both
the
metal
(
Be)
and
its
oxide
(
BeO).
3The
TDOP
cannot
take
credit
for
240Pu
poisoning.
4See
Table
4.4­
1,
Summary
of
FGE
Limits.
HNF­
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HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
3.3.3.2
Compliance
and
Verification
See
Subsection
4.4.1.2
of
this
Certification
Plan.

3.3.4
TRU
Alpha
Activity
Concentration
3.3.4.1
Requirements
TRU
waste
payload
containers
shall
contain
more
than
100
nCi/
g
of
alpha­
emitting
TRU
isotopes
with
half­
lives
greater
than
20
years.
Without
taking
into
consideration
the
TMU,
the
TRU
alpha
activity
concentration
for
a
payload
container
is
determined
by
dividing
the
TRU
alpha
activity
of
the
waste
by
the
weight
of
the
waste.
The
weight
of
the
waste
is
the
weight
of
the
material
placed
into
the
payload
container
(
i.
e.,
the
net
weight
of
the
container).
The
weight
of
the
waste
is
typically
determined
by
subtracting
the
tare
weight
of
the
payload
container
(
including
the
weight
of
the
rigid
liner
and
any
shielding
external
from
the
waste,
if
applicable)
from
the
gross
weight
of
the
payload
container.
In
the
event
waste
containers
(
e.
g.,
55­
gallon
drums)
that
have
been
radioassayed
are
overpacked
in
a
payload
container
(
e.
g.,
in
an
SWB),
sites
shall
sum
the
individual
TRU
alpha
activity
values
of
the
individual
waste
containers
and
divide
by
the
sum
of
the
individual
net
waste
weights
(
i.
e.,
less
container,
shielding,
and
liner
weights
as
appropriate)
to
determine
the
activity
per
gram
for
the
payload
container.
Waste
containers
selected
for
payload
management
shall
comply
with
the
policy
for
the
management
of
TRU
alpha
activity
concentrations.
Loading
a
55­
gallon
pipe
overpack
with
cans
is
considered
direct
loading
 
not
overpacking
for
the
purposes
of
calculating
the
weight
of
the
container.
The
TRU
alpha
activity
concentration
shall
be
reporting
to
the
WWIS;
however,
there
are
no
reporting
requirements
for
its
associated
TMU.

3.3.4.2
Compliance
and
Verification
NDA
personnel
measure
TRU
alpha
activity
concentration
in
accordance
with
the
NDA
process
described
in
Appendix
E.
Assay
data
are
validated
and
verified
at
WRAP
in
accordance
with
WMP­
350,
Section
2.3,
or
at
PFP
in
accordance
with
FSP­
PFP­
5­
8,
Section
16.2,
and
submitted
in
batch
data
reports
to
the
site
project
office
(
SPO).
The
WCO
confirms
TRU
alpha
activity
in
accordance
with
WMP­
400,
Section
7.1.8,
and
reports
it
to
WWIS
in
accordance
with
WMP­
400,
Section
7.1.5.
(
There
are
no
reporting
requirements
for
the
TRU
alpha
activity
TMU.)
Project
personnel
manage
waste
containers
with
TRU
alpha
activity
concentrations
that
do
not
exceed
100
nCi/
g
as
low­
level
waste.

Hanford
is
not
implementing
payload
management.

3.3.5
239Pu
Equivalent
Activity
(
PE­
Ci)

3.3.5.1
Requirements
239Pu
equivalent
curie
(
PE­
Ci)
quantities
shall
be
calculated
in
accordance
with
Appendix
E
for
each
payload
container.
Assay
methods
will
be
approved
by
CBFO
before
use.
In
accordance
with
the
limits
stated
in
Table
3.3­
3,
PE­
Ci
quantities
shall
be
limited
to
the
following
for
each
payload
container.
HNF­
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REV
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59
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2005
HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
Table
3.3­
3
PE­
Ci
Limits
Waste
Container
Packing
Configuration
PE­
Ci
Limit
Direct
load
 
all
approved
waste
forms
 
80
Direct
load
 
solidified/
vitrified
waste
only
 
1,800
Overpacked
into
an
85­
gal.
drum,
SWB,
or
TDOP
 
all
approved
waste
forms
 
1,100
55­
gal.
drum
in
good
condition
Overpacked
into
an
85­
gal.
drum,
SWB,
or
TDOP
 
solidified/
vitrified
waste
only
 
1,800
Overpacked
into
an
85­
gal.
drum,
SWB,
or
TDOP
 
all
approved
waste
forms
 
80,
 
130,
 
130
respectively
55­
gal.
drum
in
damaged
condition
Overpacked
into
an
85­
gal.
drum,
SWB,
or
TDOP
 
solidified/
vitrified
waste
only
 
1,800
55­
gal.
pipe
overpack
in
good
condition
Direct
load
 
all
approved
waste
forms
 
1,800
Direct
load
 
all
approved
waste
forms
 
80
Direct
load
 
solidified/
vitrified
waste
only
 
1,800
Overpacked
into
a
TDOP
 
all
approved
waste
forms
 
1,100
85­
gal.
drum
in
good
condition
Overpacked
into
a
TDOP
 
solidified/
vitrified
waste
only
 
1,800
Overpacked
into
a
TDOP
 
all
approved
waste
forms
 
130
85­
gal.
drum
in
damaged
condition
Overpacked
into
a
TDOP
 
solidified/
vitrified
waste
only
 
1,800
Direct
load
(
or
a
bin)
 
all
approved
waste
forms
 
130
Direct
load
(
or
a
bin)
 
solidified/
vitrified
waste
only
 
1,800
Overpacked
into
a
TDOP
 
all
approved
waste
forms
 
1,100
SWB
in
good
condition
Overpacked
into
a
TDOP
 
solidified/
vitrified
waste
only
 
1,800
Overpacked
into
a
TDOP
 
all
approved
waste
forms
 
130
SWB
in
damaged
condition
Overpacked
into
a
TDOP
 
solidified/
vitrified
waste
only
 
1,800
Direct
load
 
all
approved
waste
forms
 
130
TDOP
in
good
condition
Direct
load
 
solidified/
vitrified
waste
only
 
1,800
PE­
Ci
quantities
shall
be
reported
to
WIPP
using
WWIS.
There
are
no
TMU
reporting
requirements.
HNF­
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HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
3.3.5.2
Compliance
and
Verification
NDA
personnel
calculate
the
activity
of
the
CH
TRU
waste
container
as
PE­
Ci
according
to
the
methodology
in
Appendix
E
and
report
this
to
WIPP
using
WWIS.
Project
personnel
identify
payload
containers
exceeding
limits
stated
in
table
3.3­
3,
segregate
them,
and
disposition
them
in
accordance
with
approved
nonconformance
and
corrective
action
management.
The
WCO
verifies
compliance
of
the
PE­
Ci
limits
in
accordance
with
WMP­
400,
Section
7.1.8.
PE­
Ci
quantity
will
be
reported
in
WWIS
consistent
with
WMP­
400,
Section
7.1.5.
(
There
are
no
reporting
requirements
for
PE­
Ci
TMU.)

3.3.6
Radiation
Dose
Rate
3.3.6.1
Requirements
The
external
radiation
dose
equivalent
rate
of
individual
payload
containers
shall
be
limited
to
 
200
mrem/
hr
at
contact
with
the
exception
of
the
S100
pipe
overpacks
which
are
limited
to
 
179
mrem/
h
at
contact.
The
external
radiation
dose
equivalent
rate
of
the
TRUPACT­
II
shall
be
 
200
mrem/
h
at
contact
and
 
10
mrem/
hr
at
2
meters,
as
specified
in
3.3.5
of
the
CH­
WAC.
Internal
payload
container
shielding
shall
not
be
used
to
meet
these
requirements,
except
for
authorized
shielded
payload
container
configurations
such
as
the
use
of
55­
gallon
drums
containing
a
pipe
component.
In
addition,
S100
and
S200
pipe
overpacks
shall
meet
the
curie
limits
in
section
3.3
of
the
CH­
TRAMPAC.
Total
dose
rate,
including
neutron
contributions
shall
be
reported
for
each
payload
container
in
the
WWIS.

3.3.6.2
Compliance
and
Verification
For
dose
rate
measurement,
see
subsection
4.4.2.2.
These
measurements
will
be
reported
to
WIPP
using
WWIS
consistent
with
WMP­
400,
Section
7.1.5.

3.3.7
Decay
Heat
3.3.7.1
Requirements
The
decay
heat
for
each
payload
container
plus
its
TMU
shall
be
less
than
or
equal
to
the
limit
of
the
assigned
shipping
category
specified
in
Section
5.2.3
of
the
CH­
TRAMPAC.

For
all
other
approved
Content
Codes
to
be
shipped
in
payload
containers
that
exceed
the
decay
heat
limit
of
the
assigned
shipping
category,
a
determination
of
compliance
with
the
flammable
(
gas/
VOC)
limit
as
specified
in
the
CH­
TRAMPAC
allows
the
payload
container
to
be
shipped
in
the
TRUPACT­
II
package,
respectively,
under
test
category
(
also
refer
to
section
3.5.5
in
the
CH­
WAC).
The
values
calculated
for
decay
heat
and
its
associated
TMU
(
expressed
in
terms
of
one
standard
deviation)
shall
be
reported
to
the
WWIS
for
each
payload
container.
The
total
decay
heat
from
all
payload
containers
shall
be
less
than
40
watts
in
a
TRUPACT­
II.

3.3.7.2
Compliance
and
Verification
See
subsection
4.6.1.2.
HNF­
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HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
3.4
PHYSICAL
PROPERTIES
CRITERIA
AND
REQUIREMENTS
3.4.1
Residual
Liquids
3.4.1.1
Requirements
Liquid
waste
is
prohibited
at
WIPP.
Residual
liquids
containing
PCBs
are
prohibited
at
WIPP.
CH
TRU
waste
shall
contain
as
little
residual
liquid
as
is
reasonably
achievable
by
pouring,
pumping,
and/
or
aspirating.
Internal
containers
(
e.
g.,
bottles,
cans)
shall
contain
less
than
1
inch
(
2.5
cm)
of
liquid
in
the
bottom
of
the
container.
The
aggregate
volume
of
residual
liquid
in
a
payload
container
shall
be
less
than
1
percent
by
volume
of
the
container.
For
sites
that
choose
to
use
VE
in
lieu
of
NDE,
the
detection
of
any
liquid
waste
in
nontransparent
inner
containers,
detected
from
shaking
the
container,
will
be
handled
by
assuming
that
the
container
is
filled
with
liquid
and
adding
this
volume
to
the
total
liquid
volume
for
the
payload
container.

3.4.1.2
Compliance
and
Verification
See
subsection
4.3.6.2.

3.4.2
Sealed
Containers
3.4.2.1
Requirements
Sealed
containers
that
are
greater
than
4
liters
(
nominal)
are
prohibited
except
for
Waste
Material
Type
II.
2
packaged
in
a
metal
container.
All
waste
containers
with
unvented
rigid
containers
greater
than
4
liters
(
exclusive
of
rigid
poly
liners)
shall
be
subject
to
innermost
layer
of
containment
sampling
or
shall
be
vented
prior
to
initiating
drum
age
and
equilibrium
criteria.
To
satisfy
both
of
these
requirements,
payload
containers
shall
be
verified
to
be
free
of
sealed
containers
greater
than
4
liters.

3.4.2.2
Compliance
and
Verification
See
subsection
4.3.8.2.

3.5
CHEMICAL
PROPERTIES
CRITERIA
AND
REQUIREMENTS
3.5.1
Pyrophoric
Materials
3.5.1.1
Requirements
Pyrophoric
radioactive
materials
shall
be
present
only
in
small
residual
amounts
(
less
than
1
percent
by
weight)
in
payload
containers
and
shall
be
generally
dispersed
in
the
waste.
Radioactive
pyrophorics
in
concentrations
equal
to
or
greater
than
1
percent
by
weight
and
all
nonradioactive
pyrophorics
shall
be
reacted
(
or
oxidized)
and/
or
otherwise
rendered
nonreactive
before
placement
in
the
payload
container.
Nonradionuclide
pyrophoric
materials
are
not
acceptable
at
WIPP.
HNF­
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HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
3.5.1.2
Compliance
and
Verification
See
subsection
4.5.1.2.

3.5.2
Hazardous
Waste
3.5.2.1
Requirements
Hazardous
wastes
not
occurring
as
co­
contaminants
with
TRU
wastes
(
non­
mixed
hazardous
wastes)
are
not
acceptable
at
WIPP.
Each
CH
TRU
mixed
waste
container
shall
be
assigned
one
or
more
hazardous
waste
codes
as
appropriate.
Only
EPA
hazardous
waste
codes
listed
as
allowable
in
the
Hazardous
Waste
Facility
Permit
may
be
managed
at
WIPP.
Some
of
the
waste
may
also
be
identified
by
unique
state
hazardous
codes.
These
wastes
are
acceptable
at
WIPP
as
long
as
the
Treatment,
Storage,
and
Disposal
Facility
waste
acceptance
criteria
are
met.
Wastes
exhibiting
the
characteristic
of
ignitability,
corrosivity,
or
reactivity
(
EPA
hazardous
waste
numbers
of
D001,
D002,
or
D003)
are
not
acceptable
at
WIPP.
In
the
context
of
the
CH­
WAC,
hazardous
waste
codes
are
synonymous
with
hazardous
waste
numbers.

3.5.2.2
Compliance
and
Verification
Project
personnel
review
AK
information
and
implement
one
or
more
of
the
procedures
identified
in
Appendix
A
to
characterize
waste
streams
through
headspace­
gas
sampling
and
analysis
(
on
all
waste
containers)
and
homogeneous
waste
sampling
and
analysis
(
for
nondebris
waste
streams).
For
homogeneous
waste
streams,
toxicity
characteristic
and
spent
solvent
EPA
hazardous
waste
numbers
are
assigned
based
upon
the
analytical
results
and
AK.
For
debris
waste,
EPA
hazardous
waste
numbers
are
assigned
based
on
AK.
Toxicity
characteristic
(
TC)
and
spent
solvent
EPA
hazardous
waste
numbers
are
assigned
to
debris
waste
streams
based
on
headspace­
gas
sampling
and
analytical
results
if
AK
indicates
the
waste
might
contain
a
constituent
in
excess
of
the
regulatory
level.
If
data
are
insufficient
to
demonstrate
that
the
concentration
of
the
constituent
is
less
than
the
regulatory
level,
the
EPA
hazardous
waste
number
for
the
identified
constituent
is
applied
to
the
waste
stream.
The
SPM
(
or
designee)
reviews
the
analytical
data
to
ensure
that
chemical
constituents
in
the
waste
are
allowable
(
section
3.5.2
of
the
CH­
WAC).
At
the
discretion
of
the
SPM,
additional
sampling
of
the
waste
stream
from
which
any
nonconforming
container
originated
may
be
performed
to
determine
whether
the
container
is
anomalous
or
is
representative
of
the
entire
waste
stream.

Project
personnel
identify
hazardous
constituents
in
CH
TRU
wastes
and
record
the
data
in
accordance
with
applicable
data
management
procedures.
The
WCO
verifies
that
data
are
entered
in
the
WWIS.
The
TCO
ensures
the
uniform
hazardous
waste
manifest
(
UHWM)
reflects
the
hazardous
waste
codes
as
described
in
WMP­
400,
Section
2.1.5,
The
TCO
and
WCO
confirm
the
hazardous
waste
criteria
in
accordance
with
WMP­
400,
Sections
2.1.5
and
7.1.8
respectively.
HNF­
2600,
REV
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HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
3.5.3
Chemical
Compatibility
3.5.3.1
Requirements
CH
TRU
mixed
waste
must
not
contain
chemicals
that
would
cause
adverse
reactions
with
other
payload
containers
during
handling
or
disposal.
The
CH
TRU
mixed
waste
must
be
compatible
with
backfill,
seal,
and
panel
closure
materials
at
the
WIPP
facility;
container
and
packaging
material;
and
other
waste.
Only
wastes
that
have
been
shown
to
meet
the
requirements
consistent
with
section
3.5.3
of
the
CH­
WAC
are
acceptable
at
WIPP.

Other
chemicals
or
materials
not
consistent
with
the
chemicals
listed
in
the
CH­
TRAMPAC,
Tables
4.3­
1
through
4.3­
8,
as
applicable.
Other
chemicals
or
materials
not
identified
in
these
tables
are
allowed
provided
that
they
meet
the
requirements
as
specified
in
Section
4.3.1
of
the
CH­
TRAMPAC.

3.5.3.2
Compliance
and
Verification
See
subsection
4.5.4.2.

3.5.4
Explosives,
Corrosives,
and
Compressed
Gases
3.5.4.1
Requirements
Waste
shall
contain
no
explosives,
corrosives,
or
compressed
gases
(
pressurized
containers).

3.5.4.2
Compliance
and
Verification
See
subsection
4.5.2.2.

3.5.5
Headspace
Gas
VOC
Concentrations
3.5.5.1
Requirements
The
headspace
gas
of
payload
containers
shall
be
sampled
and
analyzed
in
accordance
with
HNF­
2599,
as
defined
in
the
WIPP­
WAP,
to
determine
volatile
organic
compound
(
VOC)
concentrations.

Flammable
VOCs
are
restricted
to
equal
to
or
less
than
500
ppm
in
the
payload
container
headspace.
For
those
payload
containers
that
exceed
the
flammable
VOC
limit,
a
determination
of
compliance
with
the
flammable
(
gas/
VOC)
concentration
limit
as
described
in
the
CHTRAMPAC
allows
the
payload
container
to
be
shipped
under
the
test
category.

Test
category
payload
containers
shall
be
tested
to
determine
if
all
applicable
limits
are
met
for
hydrogen/
methane,
VOC,
and
total
gas
generation
rates
(
as
appropriate)
HNF­
2600,
REV
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HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
3.5.5.2
.
Compliance
and
Verification
Headspace­
gas
sampling
of
payload
containers
shall
be
sampled
and
analyzed
in
accordance
with
HNF­
2599.
Hydrogen/
methane
sampling
of
payload
containers
shall
be
done
in
accordance
with
Appendix
F
and
site
procedure
LA­
523­
426,
Determination
of
Permanent
Gases
in
TRU
Waste
Container
Headspace.
Evaluation
of
results
is
done
in
accordance
with
subsection
4.6.2
of
this
Certification
Plan.

3.5.6
Polychlorinated
Biphenyl
3.5.6.1
Requirements
TRU
and
TRU­
mixed
wastes
which
by
virtue
of
their
form
and
content
may
be
disposed
of
in
a
chemical
waste
landfill
may
be
disposed
of
at
WIPP.
For
TRU
and
TRU­
mixed
wastes
containing
PCBs,
the
payload
container
data
entered
into
the
WWIS
shall
include
the
earliest
date
of
waste
generation
(
i.
e.,
the
date
of
removal
from
service
for
disposal),
the
date
of
waste
certification
for
disposal,
and
the
date
the
waste
was
sent
to
the
WIPP
for
disposal.
Additionally,
the
estimated
weight
of
the
PCBs
in
kilograms
(
as
recorded
on
the
uniform
hazardous
waste
manifest)
and
a
description
of
the
type
of
PCB
waste
(
e.
g.,
PCB
remediation
waste,
PCB
bulk
product
waste,
etc.)
shall
be
entered
into
the
WWIS.
Special
handling
requirements
for
shipping
TRU
and
TRU­
mixed
wastes
containing
PCBs
to
WIPP
necessitates
that
sites
notify
the
WIPP
Shipment
Scheduler
at
least
10
days
prior
to
its
shipment
date.
In
accordance
with
the
revised
WIPP
Record
of
Decision,
Hanford
is
authorized
to
ship
TRU
and
TRU­
mixed
wastes
containing
PCBs
to
WIPP.
PCB
contaminated
liquids
will
not
be
shipped
to
WIPP.

3.5.6.2
Compliance
and
Verification
The
AK
Data
Collector
will
collect
pertinent
information
regarding
PCB
items
and
waste
streams
to
support
data
entry
into
WWIS
in
accordance
with
WMP­
400,
Section
7.1.9.

The
WCO
or
alternate
confirms
that
required
PCB
information
is
correctly
entered
into
WWIS.
The
TCO
or
alternate
assures
timely
notification
of
PCB
waste
shipments
are
provided
to
the
WIPP
Shipment
Scheduler
in
accordance
with
WMP­
400,
Section
2.1.5.

3.6
DATA
PACKAGES
CONTENTS
3.6.1
Characterization
and
Certification
Data
3.6.1.1
Requirements
Sites
shall
prepare
a
WSPF
for
each
waste
stream.
Each
WSPF
shall
be
approved
by
the
CBFO
before
the
first
shipment
of
that
waste
stream.
Characterization
and
certification
information
for
each
payload
container
shall
be
submitted
to
the
WWIS
and
approved
by
the
data
administrator.
Sites
are
required
to
estimate
the
CPR
weights
and
report
these
estimates
in
the
WWIS
on
a
payload
container
basis.
Any
payload
container
from
a
waste
stream
that
has
not
been
preceded
by
an
appropriate
certified
WSPF
is
not
acceptable
at
WIPP.
HNF­
2600,
REV
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HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
3.6.1.2
Compliance
and
Verification
Project
personnel
verify
compliance
with
the
data
package
requirements
by
reviewing
data
packages
in
accordance
with
WMP­
400,
Section
7.1.6,
"
Transuranic
Waste
Project­
Level
Data
Validation
and
Verification."
The
TCO
and
WCO
ensure
the
WWIS
data
are
entered
into
the
system
and
transmitted
to
the
WIPP
for
approval
before
waste
shipment
in
accordance
with
WMP­
400,
Section
7.1.5.

The
TCO
and
WCO
verify
the
WSPF
is
complete
and
approved
in
WWIS
consistent
with
WMP­
400,
Sections
7.1.1
and
7.1.5.

3.6.2
Shipping
Data
3.6.2.1
Requirements
The
TCO
shall
complete
payload
container
transportation
certification
documents
(
PCTCDs)
or
overpack
payload
container
transportation
certification
documents
(
OPCTCDs)
and
authorize
the
TRUPACT­
II
package
for
shipment
by
completing
and
signing
the
PATCD.
Sites
shall
also
prepare
a
bill
of
lading
(
BOL)
for
CH
TRU
waste
shipments
in
accordance
with
49
CFR
Part
172,
Subpart
C,
or
UHWM
in
accordance
with
40
CFR
§
262.23,
and
an
LDR
notification
in
accordance
with
the
State
of
New
Mexico
Hazardous
Waste
Management
regulations,
as
applicable.
The
LDR
notification
for
CH
TRU
waste
shipments
shall
state
that
the
waste
is
not
prohibited
from
land
disposal.

3.6.2.2
Compliance
and
Verification
The
TCO
or
alternate
confirms
that
the
auditable
data
package
is
complete
in
accordance
with
WMP­
400,
Section
2.1.5.
If
deficiencies
are
identified,
the
TCO
and
SPM
resolve
any
deficiencies,
and
the
data
package
is
reviewed
again.

The
TCO
prepares
a
TRUPACT­
II
PCTCD
or
OPCTCD
in
accordance
with
the
CH­
TRAMPAC
for
each
payload
container
before
loading
the
container
into
a
TRUPACT­
II.
The
TCO
completes
the
PCTCD
or
OPCTCD
to
certify
an
individual
payload
container
and
a
PATCD
to
certify
the
payload
assembly
for
shipping
in
accordance
with
WRP1­
OP­
0521,
"
Receive
and
Load
TRUPACT
Containers,"
which
is
based
on
Section
6.0
of
the
CH­
TRAMPAC.
Transportation
and
Packaging
(
T&
P)
personnel
prepare
a
BOL
or
UHWM
at
the
direction
of
the
TCO.
For
nonmixed
waste
shipments,
a
BOL
is
prepared
in
accordance
with
the
requirements
of
49
CFR
172,
Subpart
C.
A
UHWM
is
prepared
for
mixed
waste
shipments
in
accordance
with
40
CFR
262.23.
With
the
initial
shipment
of
each
TRU
mixed
waste
stream,
an
LDR
one­
time
notification
shall
be
prepared
by
the
TCO
or
at
the
direction
of
the
TCO,
consistent
with
40
CFR
268.7.
Shipping
data
are
prepared
in
accordance
with
WMP­
400,
Section
2.1.5,
(
consistent
with
the
CH­
WAC,
WIPP­
WAP,
and
CH­
TRAMPAC).

The
project
records
custodian
maintains
the
generator
copy
of
the
BOL,
LDR,
and/
or
the
UHWM,
as
applicable,
on
file
in
accordance
with
WMP­
400,
Section
1.5.1.
HNF­
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HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
T&
P
personnel
perform
final
inspection
and
approval
of
the
shipping
documents.
Transportation
procedures
are
included
in
WMP­
400,
Section
2.1.5.

4.0
HANFORD
COMPLIANCE
PLAN
FOR
CH­
TRAMPAC
This
section
describes
CH
TRU
waste
management
practices
and
procedures
used
at
the
Hanford
site
to
demonstrate
compliance
with
the
CH­
TRAMPAC.
The
Hanford
site
must
demonstrate
compliance
with
CH­
TRAMPAC
transportation
requirements
before
TRU
wastes
can
be
shipped
from
the
Hanford
site
in
the
TRUPACT­
II
package
certified
for
transporting
CH
TRU
wastes.

This
section
is
organized
to
correlate
with
the
organization
of
the
CH­
TRAMPAC,
which
defines
payload
requirements
under
the
following
categories:

 
Container
and
physical
properties
 
Nuclear
properties
 
Chemical
properties
 
Gas
generation
 
Payload
assembly
 
Quality
assurance.

Each
CH­
TRAMPAC
requirement
is
summarized,
followed
by
descriptions
of
the
Hanford
site
methods
of
compliance
and
verification.
Each
generator
or
storage
site
shall
select
and
implement
a
single
method,
or
a
combination
of
methods,
to
ensure
the
payload
is
compliant
with
each
requirement
and
is
qualified
for
shipment.
Because
many
of
the
CH­
TRAMPAC
requirements
overlap
CH­
WAC
requirements,
this
section
will
refer
to
applicable
sections
and
tables
in
section
3.0
of
this
Certification
Plan,
where
appropriate.
QA
is
addressed
in
section
5.0
of
this
certification
plan.
Appendix
A
(
consistent
with
HNF­
2599)
lists
the
CH­
WAC
and
CHTRAMPAC
requirements
and
identifies
applicable
Hanford
site
documents
and
procedures
that
implement
each
requirement.
Appendix
A
(
consistent
with
HNF­
2599)
is
organized
to
correlate
with
section
numbering
for
CH­
WAC
requirements.
Therefore,
the
equivalent
compliance
and
verification
subsections
of
section
4.0
are
cross­
referenced
in
column
two
of
Appendix
A
(
consistent
with
HNF­
2599)
to
the
applicable
CH­
WAC
requirement(
s)
listed
in
column
one
of
Appendix
A.
Radiography
requirements
are
addressed
in
HNF­
2599.

Only
wastes
from
a
properly
characterized
and
approved
waste
stream
can
be
certified
as
meeting
the
requirements
and
associated
criteria
in
this
certification
plan.
Any
payload
containers
with
unresolved
discrepancies
associated
with
hazardous
waste
characterization
will
not
be
managed
or
disposed
at
WIPP
until
the
discrepancies
are
resolved
in
accordance
with
requirements
established
in
the
WIPP­
WAP.
Corrective
action
reports
applicable
to
WIPP­
WAP
requirements
shall
be
resolved
before
waste
shipment.
Throughout
this
section
and
the
discussion
of
compliance
and
verification
methods,
unless
otherwise
noted,
if
a
requirement
is
not
met,
project
personnel
segregate
the
noncompliant
item
and
initiate
an
NCR
or
CAR
in
accordance
with
WMP­
400,
Section
1.3.2,
or
Section
1.3.3.
Corrective
action
will
be
taken
in
accordance
with
WMP­
400,
Section
1.3.1,
to
resolve
nonconformances.
(
See
subsection
5.3
of
this
Certification
Plan
for
more
information
about
the
NCR/
CAR
process.)
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HANFORD
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WASTE
CERTIFICATION
PLAN
Hanford
will
ensure
compliance
with
each
waste
container
and
payload
before
shipment.
Compliance
will
be
consistent
with
one
or
more
methods
described
below.

1.
Visual
Examination.
Visual
examination
(
VE)
at
the
time
of
waste
generation
(
i.
e.,
VE
technique)
may
be
used
to
qualify
waste
for
transport.
The
operator(
s)
of
a
waste­
generating
area
shall
visually
examine
the
physical
form
of
the
waste
according
to
site/
equipment­
specific
procedures
and
remove
all
prohibited
waste
forms
before
its
placement
in
the
payload
container.
Observation
of
the
wastegeneration
process
by
an
independent
operator
may
be
used
as
an
independent
verification
of
compliance
before
closure
of
the
payload
container.
VE
under
a
sampling
program
may
be
used
to
verify
the
absence
of
prohibited
items.

2.
Visual
Inspection.
Visual
inspection
may
be
used
to
evaluate
compliance
with
specific
restrictions
(
e.
g.,
visual
inspection
of
payload
container
type,
marking,
number
of
filters,
etc.).
Visual
inspection
by
a
second
operator
may
be
considered
independent
verification.

3.
Real­
Time
Radiography
(
RTR).
RTR
may
be
used
as
an
independent
verification
to
qualify
waste
for
transport.
RTR
shall
be
used
to
nondestructively
examine
the
physical
form
of
the
waste
and
to
verify
the
absence
of
prohibited
waste
forms,
after
the
payload
container
is
closed.
The
requirements
for
RTR
are
described
in
HNF­
2599.

4.
Records
and
Database
Information.
Information
obtained
from
existing
site
records
and/
or
databases
or
AK
of
the
process
may
be
used
as
a
basis
for
reporting
the
absence
of
prohibited
waste
forms
within
waste
containers.
This
information
may
be
verified
using
RTR
and/
or
a
waste
sampling
program
(
as
applicable).

5.
Administrative
and
Procurement
Controls.
Site­
specific
administrative
and
procurement
controls
may
be
used
to
show
the
payload
container
contents
are
monitored
and
controlled
and
to
demonstrate
the
absence
of
prohibited
items.

6.
Sampling
Programs.
Sampling
programs
may
be
used
as
an
independent
verification
of
compliance.
A
site­
specific
sampling
program
designed
to
address
all
payload
requirements
needing
verification
is
recommended.

7.
Measurement.
Direct
measurement
or
evaluation
based
on
analysis
using
the
direct
measurement
may
be
used
to
qualify
waste
(
e.
g.,
direct
measurement
of
the
weight
or
analysis
of
assay
data
to
determine
decay
heat).

4.1
CH­
TRUCON
DOCUMENT
The
Contact­
handled
Transuranic
Waste
Content
Codes
(
CH­
TRUCON)
document
is
a
catalog
of
TRUPACT­
II
authorized
contents
and
a
description
of
the
methods
used
to
demonstrate
compliance
with
the
CH­
TRAMPAC.
The
Hanford
Site
is
not
currently
implementing
the
use
of
the
HalfPACT
therefore
it
will
not
be
discussed
in
this
Certification
Plan.
All
containers
must
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HANFORD
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PLAN
have
an
approved
content
code
to
be
eligible
for
shipment
in
the
TRUPACT­
II.
Each
content
code
within
the
CH­
TRUCON
document
must
contain
the
following
elements,
as
described
below:

 
Content
Codes.
Identifies
the
two­
letter
site
abbreviation
that
designates
the
physical
location
of
the
waste
and
the
three­
digit
code
that
designates
waste
generation
relative
to
implementation
of
a
formal
certification
program
and
the
physical
and
chemical
form
of
the
waste.
Content
code
identifiers
are
defined
in
the
CH­
TRUCON
(
Table
3
and
4).
 
Content
Description.
Identifies
the
physical
form
of
the
waste
(
e.
g.,
describing
whether
it
is
inorganic
or
organic,
solidified,
or
solid).
This
is
similar
to
the
waste
material
type
descriptions
in
the
CH­
TRAMPAC.
 
Storage
Site.
Provides
the
location
of
the
waste,
if
the
location
is
different
than
the
generating
site.
 
Generating
Site.
Provides
the
location
of
waste
generation.
 
Waste
Description.
Provides
basic
information
regarding
the
nature
and
main
components
of
the
waste.
 
Generating
Source(
s).
Lists
processes
and/
or
buildings
at
each
site
that
generates
the
waste
in
each
content
code.
 
Waste
Form.
Provides
more
detailed
information
on
the
waste
contents,
how
the
waste
is
processed,
and
specific
information
about
the
chemistry
of
constituents.
 
Waste
Packaging.
Describes
in
detail
techniques
necessary
for
waste
packaging
in
a
given
content
code.
This
includes
a
description
of
the
waste
confinement
layers,
the
number
of
layers
of
confinement
used
in
packaging
waste,
and
the
mechanism
for
bag,
can,
or
container
closure.
 
Assay.
Describes
the
types
of
radioactive
materials
measurement
techniques
used
to
obtain
fissile
material
content
and
decay
heat
values
for
a
particular
content
code.
 
Liquids.
Describes
the
authorized
procedures
used
by
sites
to
ensure
the
limits
imposed
on
residual
liquids
(<
1
percent
by
volume)
are
met
for
each
content
code.
 
Explosives/
Compressed
Gases.
Identifies
the
methods
used
to
preclude
the
presence
of
explosives
or
compressed
gases
and
the
method
for
secondary
verification
of
this
requirement.
 
Pyrophorics.
Describes
the
controls
in
place
at
each
site
to
ensure
nonradionuclide
pyrophoric
materials
in
TRU
waste
are
excluded,
reacted
to
render
nonpyrophoric,
or
are
immobilized
before
placement
in
certifiable
waste
containers.
 
Corrosives.
Describes
the
controls
in
place
to
ensure
that
corrosive
materials
in
TRU
waste
are
either
not
present
or
are
neutralized
or
immobilized
before
placement
in
a
payload
container.
 
Chemical
Compatibility.
Describes
the
controls
in
place
to
ensure
chemical
compatibility
for
the
waste
contents
and
the
TRUPACT­
II.
All
chemicals/
materials
in
the
waste
for
a
specific
content
code
are
restricted
either
to
the
allowable
chemical
lists
or
to
the
limits
specified
in
the
CH­
TRAMPAC.
 
Payload
Container
Venting
and
Aspiration.
Details
how
payload
containers
that
have
been
stored
in
an
unvented
condition
(
i.
e.,
no
filter
and/
or
unpunctured
liner)
are
aspirated
using
one
of
three
options
to
ensure
equilibration
of
any
gases
that
may
have
accumulated
in
the
closed
container.
This
procedure
is
required
only
for
unvented
waste.
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HANFORD
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CERTIFICATION
PLAN
 
Additional
Criteria.
Provides
details
on
how
the
waste
qualifies
for
shipment
by
meeting
additional
transport
requirements
(
e.
g.,
filtering
payload
containers
and
puncturing
liners).
 
Shipping
Category.
Provides
the
numeric
or
alphanumeric
notation
summarizing
waste
and
waste
packaging
description
information
whereby
the
payload
container
wattage
and
gas
generation
rate
limits
can
be
derived.
 
Maximum
Allowable
Wattage.
Provides
a
limit
that
may
be
used
for
evaluating
payload
container
compliance
with
hydrogen
gas
concentration
limits.

Any
site
requiring
the
transportation
of
TRU
waste
in
the
TRUPACT­
II
that
is
not
described
in
an
approved
content
code
must
request
the
revision
or
addition
of
a
content
code
by
submitting
a
request
in
writing
to
the
WIPP
CH­
TRU
Payload
Engineer.

The
WIPP
CH­
TRU
Payload
Engineer
has
the
authority
to
review
and
approve
any
content
code
request
only
if
compliance
with
the
transportation
requirements
of
the
CH­
TRAMPAC
document
can
be
demonstrated.
Any
submittal
not
meeting
the
requirements
of
the
CH­
TRAMPAC
shall
not
be
approved
for
inclusion
in
the
CH­
TRUCON
document
or
be
used
as
the
basis
for
a
shipment
in
the
TRUPACT­
II.
The
WIPP
CH­
TRU
Payload
Engineer
does
not
have
the
authority
to
change
the
transportation
requirements
for
the
TRUPACT­
II
or
the
CH­
TRAMPAC
document
without
approval
from
the
NRC.

The
use,
operation,
and
maintenance
of
the
TRUPACT­
II
and
its
associated
payload
are
operated
under
a
QA
program
approved
by
CBFO.

Requests
for
revisions
to
content
codes
shall
be
submitted
to
the
WIPP
CH­
TRU
Payload
Engineer
and
may
include
the
following:

 
Minor
revisions
to
the
content
descriptions
(
e.
g.,
changes
to
buildings
or
sources
generating
the
waste)
 
Changes
to
method(
s)
used
to
characterize
the
waste
(
e.
g.,
the
use
of
an
alternate
approved
assay
method)
 
Changes
to
the
packaging
descriptions
(
e.
g.,
the
use
of
a
different
number
of
bag
layers)
 
Addition
of
a
new
authorized
waste
form
from
a
given
site
(
e.
g.,
shipment
of
filter
waste)
 
Minor
revisions
to
the
chemical
list
for
a
specific
content
code.

CH­
TRUCON
Document
Process
The
process
for
requesting
a
content
code
addition
or
revision
is
as
follows:

1.
The
site
prepares
a
draft
content
code
containing
sufficient
information
to
satisfy
all
of
the
necessary
elements
of
a
code,
previously
identified.
If
the
request
is
for
a
content
code
revision,
only
the
revised
elements
require
preparation
and
documentation.
The
site
shall
ensure
that
the
information
submitted
in
the
form
of
a
content
code
addition
or
revision
accurately
describes
the
waste
and
waste
generating
processes
to
the
best
of
its
knowledge.
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HANFORD
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PLAN
2.
The
site
submits
the
draft
content
code
or
content
code
elements
in
writing
to
the
WIPP
CH­
TRU
Payload
Engineer
for
review.

3.
Under
the
direction
of
the
WIPP
CH­
TRU
Payload
Engineer,
the
submittal
shall
be
reviewed
for
completeness
and
satisfactory
demonstration
of
compliance
with
all
the
transportation
requirements
of
the
CH­
TRAMPAC
This
review
may
include
a
review
to
ensure
each
of
the
previously
identified
elements
is
complete,
the
calculation
or
verification
of
new
payload
shipping
categories
to
accommodate
changes
in
packaging
configurations
using
the
Numeric
Payload
Shipping
Category
Worksheet
(
Tables
2.2­
1
through
2.2­
4
in
Appendix
2.2
of
the
CH­
TRU
Payload
Appendices),
and
the
analysis
of
compliance
with
the
list
of
allowable
materials
(
for
new
waste
forms
or
changes
in
chemical
composition).
Any
submittal
that
does
not
demonstrate
compliance
with
every
transportation
requirement
for
the
TRUPACT­
II
shall
not
be
approved
by
the
WIPP
CH­
TRU
Payload
Engineer.

4.
Upon
completion
of
the
review,
the
WIPP
CH­
TRU
Payload
Engineer
shall
send
formal
written
notification
to
the
site
indicating
the
status
of
the
request.
If
the
request
is
denied,
the
WIPP
CH­
TRU
Payload
Engineer
shall
indicate
in
the
notification
the
reason
why
the
request
was
not
accepted
and
shall
identify
which
elements
of
the
submittal
are
incomplete
or
out
of
compliance.

5.
If
the
request
is
approved,
a
site
may
begin
using
the
new
or
revised
content
code
once
official
notification
is
received
from
the
WIPP
CH­
TRU
Payload
Engineer.
Sites
may
not
use
proposed
content
code
additions
or
revisions
to
make
shipments
in
the
TRUPACT­
II
before
receipt
of
written
notification
from
the
WIPP
CHTRU
Payload
Engineer.

6.
All
content
code
additions
or
revisions
shall
be
recorded
in
the
CH­
TRUCON
document.
The
current
revision
of
the
CH­
TRUCON
document
shall
be
available
to
sites.

4.2
COMPLIANCE
PROGRAM
Transportation
Certification
Official
The
site
transportation
certification
official
(
TCO)
is
responsible
for
administratively
verifying
the
compliance
of
payload
containers
and
the
payload
assembly
with
transportation
requirements
(
CH­
TRAMPAC
and
DOT).
The
site
TCO
shall
approve
by
signature
on
the
transportation
certification
documents
every
payload
for
transport.
In
accordance
with
the
WIPP
waste
acceptance
criteria
(
CH­
WAC),
a
similar
position,
WCO,
is
responsible
for
verifying
all
waste
prepared
for
shipment
to
the
WIPP
meets
the
specified
CH­
WAC.
The
functions
of
the
two
positions
may
be
performed
by
the
same
or
different
official(
s).
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HANFORD
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WASTE
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PLAN
CBFO
The
CBFO
is
responsible
for
the
performance
of
compliance
verification
audits,
which
are
conducted
for
each
program
before
the
first
shipment
and
periodically
thereafter
to
evaluate
TRUPACT­
II
payload
compliance
and
specific
areas
of
CH­
WAC
compliance.
Compliance
verification
audits
are
not
required
at
sites
that
document
compliance
by
preparing
waste­
specific
data
packages
that
are
reviewed
and
approved
by
the
CBFO.
Audit
activities
include
document
review
and
interview
of
site
operators
on
a
job­
function
basis
relative
to
meeting
the
applicable
criteria.
Where
specific
technical
ability
is
required
(
e.
g.,
chemical
compatibility,
isotopic
inventory,
and
assay),
technical
experts
are
included
on
the
audit
team.
The
DOE­
CBFO
will
grant
or
deny
waste
certification
and
waste
transportation
authorization
based
on
objective
findings.

The
use,
operation,
and
maintenance
of
the
TRUPACT­
II
at
the
Hanford
site
is
conducted
under
the
QA
program
contained
in
section
5.0
of
this
Certification
Plan.

4.3
CONTAINER
AND
PHYSICAL
PROPERTIES
REQUIREMENTS
4.3.1
Container
Descriptions
4.3.1.1
Requirements
Only
the
following
payload
containers,
which
must
comply
with
the
specifications
in
Section
2.1,
Table
2.1­
1,
and
Section
2.9
of
the
CH­
TRAMPAC,
are
authorized
for
shipment
in
the
TRUPACT­
II:

 
55­
gallon
drums
 
Standard
pipe
overpack
 
55­
gallon
drums
with
S100,
or
S200
pipe
overpacks
 
85­
gallon
drum
(
includes
75­
to
88­
gallon
drums)
 
Standard
waste
box
(
SWB)
 
Ten­
drum
overpack
(
TDOP)
(
TRUPACT­
II
only)

The
maximum
number
of
containers
per
TRUPACT­
II
and
authorized
packaging
configurations
are
shown
in
subsection
3.2.3.1,
table
3.2­
2,
of
this
Certification
Plan.

4.3.1.2
Compliance
and
Verification
The
Hanford
site
procures
payload
containers
types
(
e.
g.,
55­
gallon
drums,
85­
gallon
drums,
SWBs,
and
TDOPs)
that
meet
the
following
requirements:

 
SWBs
and
TDOPs
are
procured
to
the
same
standards
and
specifications
as
the
containers
used
in
Type
7A
testing.
 
New
55­
and
85­
gallon
drums
are
procured
as
UN1A2,
in
accordance
with
applicable
requirements
of
49
CFR
173.
Drums
must
be
procured
to
the
same
standards
and
specifications
used
in
DOT
7A,
Type
A,
testing.
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Pipe
overpacks
(
standard,
S100
and
S200)
are
procured
in
accordance
with
specifications
identified
in
the
CH­
TRAMPAC
(
Section
2.1
and
Section
2.9).

Containers
are
inspected
to
ensure
that
they
are
DOT
Specification
17C
or
17H
or
meet
UN1A2
(
DOT
7A,
Type
A)
requirements.
Permanent
markings
embossed
on
the
bottom
of
the
drums
are
used
to
verify
the
drum
type
if
procurement
records
are
not
available.
Alternatively,
if
the
markings
are
not
visible
(
e.
g.,
drums
that
are
galvanized
through
a
dipping
process,
which
obscures
the
embossing),
the
drums
are
visually
inspected
and
inspection
results
compared
to
requirements
for
17C,
17H,
or
UN1A2
(
DOT
7A,
Type
A)
drums.
Project
personnel
examine
retrievably
stored
containers
for
compliance
with
the
applicable
requirements
and
verify
the
containers
are
in
good
and
unimpaired
condition.
The
TCO
verifies
the
container
meets
the
specific
DOT
7A,
Type
A,
criteria
and
documents
it
on
a
container
integrity
checklist
(
consistent
with
Appendix
D
of
the
CH­
WAC),
in
accordance
with
WMP­
400,
Section
2.1.5.
Project
personnel
document
their
procurement
acceptance
and/
or
visual
inspections.
If
packages
cannot
be
shown
to
meet
the
above
requirements
by
procurement
records
and/
or
physical
examination,
the
TCO
or
project
personnel
take
corrective
action
(
e.
g.,
accept
as
is
or
repackage
the
waste
into
a
certifiable
container)
to
resolve
the
nonconformance.
The
TCO
verifies
that
the
packaging
meets
applicable
requirements
and
that
the
TRUPACT­
II
is
assembled
in
an
authorized
packaging
configuration,
in
accordance
with
WRP1­
OP­
0521
and
WMP­
400,
Section
2.1.5.

Refer
to
Appendix
A,
column
"
CH­
WAC
and
Certification
Plan
Section,"
row
3.2.1,
which
contains
the
titles
of
applicable
procedures
that
implement
the
requirements
of
this
subsection.

4.3.2
Dunnage
4.3.2.1
Requirements
A
shipper
shall
use
empty
55­
gallon
drums,
85­
gallon
drums,
or
a
SWBs
as
dunnage
to
complete
payload
configuration
if
too
few
loaded
payload
containers
are
available
that
meet
transportation
requirements.
Dunnage
containers
shall
meet
the
specifications
of
section
2.9
of
the
CH­
TRAMPAC
except
that
dunnage
containers
shall
have
at
least
one
open
vent
ports
(
i.
e.,
not
filtered
or
plugged).
Dunnage
containers
shall
be
marked
in
accordance
with
subsection
4.3.4
of
this
Certification
Plan.

4.3.2.2
Compliance
and
Verification
Empty
55­
gallon
drums,
85­
gallon
drums,
or
SWBs
that
meet
DOT
Type
A
requirements
may
be
used
as
dunnage.
Dunnage
drums
may
be
assembled
into
a
seven­
pack
or
four­
pack
of
only
dunnage
drums
or
may
be
assembled
into
a
seven­
pack
or
four­
pack
with
drums
of
waste
that
meet
all
applicable
requirements.
Refer
to
subsection
4.3.4
for
requirements
for
labeling
dunnage
containers.
Loading
personnel
ensure
that
dunnage
containers
have
open
vent
ports
(
e.
g.,
vent
ports
shall
not
be
plugged
or
filtered),
in
accordance
with
WMP­
400,
Section
2.1.5.
Shoring,
including
empty
drums,
is
provided
as
necessary
inside
a
TDOP
(
only
applicable
for
shipment
in
the
TRUPACT­
II
in
accordance
with
WMP­
400,
Section
2.1.5).
The
TCO
ensures
that
dunnage
drums
meet
all
applicable
requirements
(
e.
g.,
through
visual
inspection
and
documentation
before
shipment)
in
accordance
with
WMP­
400,
Section
2.1.5,.
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Refer
to
Appendix
A,
column
"
CH­
WAC
and
Certification
Plan
Section,"
row
3.2.6,
which
contains
the
titles
of
applicable
procedures
that
implement
the
requirements
of
this
section.

4.3.3
Container/
Assembly
Weight
and
Center
of
Gravity
4.3.3.1
Requirements
Section
2.3
of
the
CH­
TRAMPAC
restricts
the
weight
of
individual
payload
containers,
the
payload
assembly,
loaded
TRUPACT­
IIs,
and
the
center
of
gravity
of
each
payload
assembly.
The
weight
limits
are
as
follows:

 
1,000
pounds
per
55­
gallon
drum
(
these
drums
must
also
meet
restrictions
in
DOT
7A,
Type
A)
 
1,000
pounds
per
85­
gallon
drum
(
these
drums
must
also
meet
restrictions
in
DOT
7A,
Type
A)
 
4,000
pounds
per
SWB
 
6,700
pounds
per
TDOP
 
328
pounds
per
55­
gallon
drum
containing
a
six­
inch­
diameter
pipe
component
(
i.
e.,
a
standard
pipe
overpack)
 
547
pounds
per
55­
gallon
drum
containing
a
twelve­
inch
diameter
pipe
component
(
i.
e.,
a
standard
pipe
overpack)
 
550
pounds
per
55­
gallon
drum
containing
a
neutron
shielded
six­
inch
diameter
component
(
i.
e.,
an
S100
pipe
overpack)
 
547
pounds
per
55­
gallon
drum
containing
a
gamma
shielded
twelve­
inch
diameter
pipe
component
(
i.
e.,
an
S200
pipe
overpack)
 
7,265
pounds
per
TRUPACT­
II
payload
assembly
including
fourteen
55­
gallon
drums,
fourteen
pipe
overpacks
(
standard,
S100,
or
S200),
eight
85­
gallon
drums,
2
SWBs,
or
one
TDOP)
(
including
pallet,
spacers,
guide
tubes,
slip­
sheets
[
optional],
reinforcing
plates,
slings,
and
banding
material)
 
19,250
pounds
per
loaded
TRUPACT­
II.

NOTE
­
Actual
payload
assembly
weights
are
limited
by
"
as­
built"
TRUPACT­
II
weights
and
DOT
requirements
for
a
loaded
tractor/
trailer.

The
center
of
gravity
requirements
are
as
follows:

 
For
TRUPACT­
II
payloads,
the
total
weight
of
payload
container(
s)
in
the
top
layer
of
the
payload
assembly
shall
be
less
than
or
equal
to
the
total
weight
of
the
payload
container(
s)
in
the
bottom
layer
of
the
payload
assembly.
 
The
total
weight
of
the
top
five
55­
gallon
or
three
85­
gallon
drums
in
a
TDOP
must
be
less
than
or
equal
to
the
total
weight
of
the
bottom
five
55­
gallon
or
three
85­
gallon
drums.

Each
payload
container
(
or
dunnage)
shall
be
weighed
on
a
calibrated
scale.
Scale
calibrations
shall
be
in
accordance
with
the
National
Institute
for
Standards
and
Testing
(
NIST)
Handbook
44
or
an
equivalent
standard.
The
weight
of
each
payload
container
and
measurement
error
must
be
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recorded
on
the
PCTCD
or
OPCTCD.
The
weight
and
error
of
the
total
TRUPACT­
II
payload
is
reported
on
the
PATCD.

4.3.3.2
Compliance
and
Verification
Loading
personnel
weigh
individual
payload
containers
in
accordance
with
WRP1­
OP­
0503,
"
Move
Containers
Throughout
WRAP
Facility,"
to
ensure
that
payload
containers
do
not
exceed
maximum
allowable
weights
determined
from
DOT
7A,
Type
A,
testing
and
evaluation,
those
shown
above,
or
table
3­
1,
whichever
is
less.
Loading
personnel
calibrate
and
maintain
the
scale
in
accordance
with
NIST
Handbook
44,
calculate
the
error,
and
record
the
calibration
results.
If
the
waste
container
meets
applicable
weight
limits,
loading
personnel
record
the
weight
of
the
container
for
each
payload
container.
The
TCO
reviews
loading
data
and
the
PCTCD
(
see
Appendix
B­
1)
or
OPCTCD
(
see
Appendix
B­
2)
to
verify
compliance
with
the
individual
payload
container
weight
requirement
and
signs
the
PCTCD
or
OPCTCD,
in
accordance
with
WMP­
400,
Section
2.1.5.
If
the
measured
weight
of
the
payload
container
(
including
the
error)
exceeds
applicable
weight
limits,
the
containers
are
repackaged
and
reweighed.

The
TRUPACT­
II
payload
weight
limit
of
7,265
pounds
includes
a
payload
of
drums,
SWBs
or
TDOP
(
for
TRUPACT­
II
only)
and
the
payload
pallet,
optional
slip­
sheets,
reinforcing
plates,
guide
tubes,
and
banding
material.
The
total
payload
weight
is
obtained
either
from
the
weights
and
associated
errors
of
the
individual
components
or
by
weighing
the
complete
assembly.
If
total
payload
weight
is
obtained
by
summing
the
weights
of
individual
payload
containers
or
dunnage
(
plus
the
weight
of
pallets,
reinforcing
plates,
slip­
sheets,
guide
tubes,
and
banding
material),
the
measurement
includes
the
square
root
of
the
sum
of
the
squares
of
the
individual
measurement
errors,
as
indicated
on
the
PATCD.
If
total
payload
is
weighed
as
an
assembly,
the
measurement
includes
the
error.
The
TCO
plans
the
load
using
the
PATCD
(
Appendix
D).
The
load
is
planned
to
ensure
compliance
with
the
center­
of­
gravity
requirements
by
placing
the
heavier
seven
pack
of
drums
or
the
heavier
SWB
at
the
bottom
of
the
TRUPACT­
II.
The
TCO
also
takes
the
actual
as­
built
weight
of
the
TRUPACT­
II
and
the
weight
of
the
payload
pallet,
optional
slip­
sheets,
reinforcing
plates,
guide
tubes,
and
banding
material
into
account
as
necessary
during
load
planning.
The
loading
personnel
load
the
TRUPACT­
II
in
accordance
with
the
requirements
of
the
PATCD,
the
Contact­
Handled
Packaging
Program
Guidance
(
DOE/
WIPP­
02­
3183),
and
the
Contact­
Handled
Packaging
Operations
Manual
(
DOE/
WIPP­
02­
3184).

The
TCO
reviews
the
data
and
information,
approves
the
weight
of
the
total
payload,
verifies
compliance
with
the
TRUPACT­
II
payload
weight
and
center­
of­
gravity
requirements
and
signs
the
PATCD.
The
TCO
also
verifies
that
TRUPACT­
II
trailer
loads
meet
all
DOT
weight
restrictions,
in
accordance
with
WMP­
400,
Section
2.1.5.
All
container
weights
are
entered
into
WWIS
before
container
and/
or
shipment
approval.
Approval
is
done
by
CBFO.

Refer
to
Appendix
A,
column
"
CH­
WAC
and
Certification
Plan
Section,"
row
3.2.2,
which
contains
the
titles
of
applicable
procedures
that
implement
the
requirements
of
this
subsection.
HNF­
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4.3.4
Container
Marking
4.3.4.1
Requirements
Each
payload
and
dunnage
container
shall
be
labeled
with
the
unique
container
identification
number
(
CIN)
and
WIPP
bar
code
(
see
subsection
3.2.5.1).

The
CIN
and
WIPP
bar
code
may
be
on
the
same
label.
If
an
empty
55­
gallon
drum
or
SWB
is
used
as
dunnage
to
complete
a
14­
drum
or
2­
SWB
payload
configuration,
the
dunnage
container
shall
be
labeled
with
the
following
information:

 
Unique
CIN
 
"
EMPTY"
or
"
DUNNAGE."

If
a
seven­
pack
of
only
dunnage
drums
or
three­
pack
of
85­
gallon
drums
or
a
dunnage
SWB
is
used
in
the
TRUPACT­
II,
the
container(
s)
shall
be
labeled
"
EMPTY"
or
"
DUNNAGE."
The
unique
CIN
labels
are
not
required
for
a
seven­
pack
of
dunnage
drums
or
a
dunnage
SWB.

4.3.4.2
Compliance
and
Verification
In
accordance
with
WRP1­
OP­
0521,
loading
facility
personnel
load
the
TRUPACT­
II
in
one
of
the
configurations
identified
in
table
3.2­
2.
If
dunnage
containers
are
used,
loading
personnel
mark
each
dunnage
container
with
a
unique
identification
number,
label
the
containers
"
EMPTY"
or
"
DUNNAGE,"
and
document
this
action.
Dunnage
drums
in
a
seven­
pack
assembly
are
reported
by
CIN
and
reported
in
the
WWIS,
consistent
with
WMP­
400,
Section
7.1.5.
If
a
seven­
pack
of
empty
drums
is
shipped
as
dunnage,
each
dunnage
container
is
labeled
"
EMPTY"
or
"
DUNNAGE,"
but
the
containers
are
not
marked
with
an
identification
number
and
not
reported
in
the
WWIS.
Payload
containers
will
be
marked
"
Caution
Radioactive
Material"
with
a
yellow
and
magenta
label
consistent
with
10
CFR
Part
835.
Those
payload
containers
that
are
RCRA
regulated
will
have
hazardous
waste
labels
affixed.
The
TCO
performs
a
visual
inspection
to
verify
whether
dunnage
containers
are
used,
whether
the
containers
are
marked
and
labeled
as
required,
and
documents
the
information
on
the
PCTCD
or
OPCTCD
and
PATCD,
waste
inspection
checklist,
and/
or
the
waste
dunnage
certification
statement
(
see
WMP­
400,
Section
2.1.5).

4.3.5
Filter
Vents
4.3.5.1
Requirements
Each
payload
container
(
except
dunnage
containers)
to
be
transported
in
the
TRUPACT­
II
must
have
one
or
more
filter
vents
as
specified
below
(
including
overpacked
containers,
as
applicable).
Table
4.3­
1
below
specifies
the
flow
and
hydrogen
diffusion
requirements
for
these
filters.
Filters
to
be
installed
on
each
waste
container
(
at
a
minimum)
are:

 
1
per
55­
gallon
drum
 
1
per
85­
gallon
drum
 
1
per
pipe
component
overpacked
in
a
drum
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1
per
filtered
metal
can
(
not
applicable
to
waste
Type
II.
2)
 
2
per
SWB
 
2
per
bin
overpacked
in
a
SWB
 
9
per
TDOP
 
1
per
sealed
bag.

The
use
of
a
heat­
sealed
filtered
bag
as
the
innermost
layer
of
confinement
to
package
CH­
TRU
waste
is
limited
to
Waste
Material
Types
I.
3,
II.
1,
III.
1,
and
III.
3
provided
that
there
is
no
potential
for
contact
of
the
filters
with
water.
Waste
Material
Types
II.
3
and
III.
2,
which
by
definition
include
a
metal
can
as
the
innermost
layer
of
confinement,
may
use
heat­
sealed
filtered
bags
as
confinement
layers
outside
of
the
innermost
metal
can.
Because
Waste
Material
Type
II.
2
(
inorganic
solids
packaged
in
metal
cans)
does
not
generate
flammable
gas,
heat­
sealed
filtered
or
unfiltered
bags
may
be
used
as
confinement
layers
outside
of
the
innermost
metal
can.
For
other
waste
material
types,
heat­
sealed
filtered
bags
are
not
allowed
as
the
innermost
layer
of
confinement.

The
use
of
filtered
bags
in
waste
packaging
configurations
must
be
specified
in
approved
content
codes.
Appendix
3.11
of
the
CH­
TRU
Payload
Appendices
describes
the
use
of
filtered
bags
as
confinement
layers
and
the
basis
for
the
increased
decay
heat
limits
for
specific
shipping
categories
using
filtered
bags.

Filter
vents
for
the
outer
payload
container
and
any
overpacked
payload
container
shall
be
legibly
marked
to
ensure
both
(
1)
identification
of
the
supplier
and
(
2)
date
of
manufacture,
lot
number,
or
unique
serial
number.

The
filter
vent
housing
and
element
for
the
outer
payload
container
shall
have
an
operating
temperature
range
from
 
40
degrees
Celsius
(
°
C)
to
+
70
°
C
(­
40
degrees
Fahrenheit
[
°
F]
to
+
158
°
F).
The
filter
vent
threads
shall
be
compatible
with
the
bung
in
the
container
or
shall
be
self­
tapping.
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Table
4.3­
1
Minimum
Filter
Vent
Specifications
Minimum
Filter
Vent
Specification
Container
Type
Flow
Rate
(
ml/
min
of
air,
STP,
at
1
inch
of
water)
a
Efficiency
(
percent)
Total
Hydrogen
Diffusivity
(
mol/
s/
mol
fraction
at
25
°
C)
b,
c
55­
Gallon
Drumd
35
>
99.9e
1.90E­
6
85­
Gallon
Drum
35
>
99.9e
3.70E­
6
Pipe
Componentf
35
NAe
1.90E­
6
Filtered
Confinement
Layer
(
e.
g.,
Metal
Can)
g
35
NAe
1.90E­
6
SWB
35
>
99.9e
7.40E­
6
Bin
35
NAe
7.40E­
6
TDOP
35
>
99.9
3.33E­
5
Filtered
Bagf
35
NAe
1.075E­
5
High­
Diffusivity
Filters
(
HDF)
HDF
(
2X)
HDF
(
5X)
HDF
(
25X)
HDF
(
100X)
35
35
35
35
>
99.9e
>
99.9e
>
99.9e
>
99.9e
7.40E­
6
1.85E­
5
9.25E­
5
3.70E­
4
High­
Diffusivity
Bag
Filters
(
HDBF)
HDBF
(
2X)
f
HDBF
(
5X)
f
HDBF
(
25X)
f
HDBF
(
100X)
f
35
35
35
35
NAe
NAe
NAe
NAe
2.150E­
5
5.375E­
5
2.688E­
4
1.075E­
3
aFilters
tested
at
a
different
pressure
gradient
shall
have
a
proportional
flow
rate
(
e.
g.,
35
ml/
min
at
1
inch
of
water
=
1
Liter/
minute
at
1
pound
per
square
inch).
bTotal
hydrogen
diffusivity
may
be
achieved
through
the
use
of
multiple
filter
vents.
cFilters
exceeding
these
specifications
may
be
used
to
decrease
the
resistance
to
hydrogen
diffusivity
in
accordance
with
the
logic
outlined
in
Appendix
2.2
of
the
CH­
TRU
Payload
Appendices.
dThe
use
of
equivalent
venting
mechanisms
is
not
allowed
for
55­
gallon
drums
used
as
part
of
the
pipe
overpack
configuration.
eFilters
installed
in
payload
containers
that
are
overpacked
in
drums,
SWBs,
or
TDOPs
are
exempt
from
the
efficiency
requirement
as
the
outer
payload
container
must
exhibit
a
>
99.9
percent
efficiency.
fThe
use
of
equivalent
venting
mechanisms
is
not
allowed.
gFiltered
confinement
layer
specification
is
not
applicable
to
Waste
Material
Type
II.
2
(
packaged
in
a
metal
can)
due
to
zero
gas
generation
potential.

ml/
min
=
Milliliter(
s)
per
minute
mol/
s/
mol
fraction
=
Moles
per
second
per
mole
fraction
NA
=
Not
applicable
STP
=
Standard
temperature
and
pressure
4.3.5.2
Compliance
and
Verification
The
Hanford
site
procures
filters
for
use
on
CH­
TRU
waste
containers
that
are
specified
on
WIPP
web
site
http://
www.
WIPP.
ws/
Library/
WAC/
FilterVents.
pdf.
Filters
must
meet
the
HNF­
2600,
REV
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HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
specifications
described
in
Section
4.3.5.1,
of
the
this
certification
plan
and
Section
B1
of
HNF­
2599,
as
applicable,
and
are
procured
in
accordance
with
the
Hanford
site's
procurement
process.

Project
personnel
visually
verify
that
drum
filter
vents
and
bag
filter
vents,
if
present,
have
been
installed
properly
as
shown
in
TRU­
OP­
001,
"
Headspace
Gas
Samples
of
TRU
Waste
Containers";
ZO­
170­
044,
Load
Standard
Waste
Box
(
SWB)
Storage
Containers
With
TRU
Waste;
ZO­
160­
080,
"
Pipe­
N­
Go
Processing";
ZO­
170­
057,
"
Visual
Examination
Technique
for
PFP
Debris
Waste";
WRP1­
OP­
0503,
"
Move
Containers
Throughout
WRAP
Facility";
or
WRP1­
OP­
0522,
"
Assemble
and
Stretch
Wrap
TRUPACT­
II
Payload."
If
container
filter
vents
are
not
installed,
project
personnel
procure
filter
vents
that
meet
specifications
and
install
the
correct
number
of
filter
vents.
The
TCO
verifies
and
records
this
information
on
the
PCTCD
or
OPCTCD,
in
accordance
with
WMP­
400,
Section
2.1.5.
Filters
not
meeting
these
requirements
are
replaced
as
necessary.

Previously
unvented
containers
shall
meet
the
aspiration
requirements
described
in
WMP­
400,
Section
7.1.8.
The
WCO
verifies
and
records
the
aspiration
methods
as
appropriate
in
accordance
with
WMP­
400,
Section
7.1.8.

Refer
to
Appendix
A,
column
"
CH­
WAC
and
Certification
Plan
Section,"
row
3.2.6,
which
contains
the
titles
of
applicable
procedures
that
implement
the
requirements
of
this
subsection.

4.3.6
Liquids
4.3.6.1
Requirements
Liquid
waste
is
prohibited
in
the
payload
containers,
except
for
residual
amounts
in
well­
drained
containers.
Residual
liquids
containing
PCBs
are
prohibited
at
WIPP.
The
total
volume
of
residual
liquid
in
a
payload
container
shall
be
less
than
1
percent
by
volume
of
the
payload
container,
consistent
with
section
2.6
of
the
CH­
TRAMPAC.

4.3.6.2
Compliance
and
Verification
Generators
ensure
TRU
waste
is
not
in
free­
liquid
form,
minor
residual
liquids
remaining
in
internal
containers
(
e.
g.,
bottles,
cans)
do
not
exceed
1
inch
(
2.5
cm)
in
the
bottom
of
any
container,
and
the
total
liquid
in
the
waste
package
does
not
exceed
1
volume
percent.
Very
small
amounts
of
liquid
identified
in
items
other
than
internal
containers
(
e.
g.,
vials,
ampules,
levels,
etc.)
may
be
considered
residual
and,
therefore,
are
acceptable
consistent
with
40
CFR
§
264.314(
a).

Initially,
AK
is
used
to
determine
container
contents
and
presence
of
PCBs.
AK
is
confirmed
through
radiography
and/
or
VE
for
retrievably
stored
waste.
If
PCBs
are
determined
by
AK
to
be
present
in
a
waste
stream,
radiography
or
VE
technique
will
be
used
to
verify
liquids
are
not
present.
AK
is
verified
through
the
VE
technique
at
the
time
of
packaging
for
newly
generated
waste.
Waste
generators
ensure
that
the
contents
of
newly
generated
waste
containers
comply
with
the
liquids
restriction.
For
retrievably
stored
waste,
project
personnel
estimate
liquid
volume
by
radiography
and/
or
VE,
in
accordance
WMP­
400,
Section
7.1.3,
"
TRU
Waste
Repackaging,
Visual
Examination
and
Sampling,"
WRP1­
OP­
0908,
"
Operation
of
the
Drum
HNF­
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Nondestructive
Examination
System,"
and
applicable
procedures
listed
in
Appendix
A,
and
record
the
location
of
any
liquid
detected
in
a
CH
TRU
waste
container.
NDE
and/
or
VE
personnel
reject
payload
containers
found
to
have
greater
than
1
volume
percent
liquid
or
greater
than
1
inch
of
liquid
in
the
bottom
of
an
internal
container
and
segregate
them.
If
necessary,
personnel
repackage
noncompliant
waste
containers
in
accordance
with
WMP­
400,
Section
7.1.3.
The
TCO
verifies
compliance
on
the
PCTCD
or
OPCTCD,
in
accordance
with
WMP­
400,
Section
2.1.5.

Refer
to
Appendix
A,
column
"
CH­
WAC
and
Certification
Plan
Section,"
row
3.4.1,
which
contains
the
titles
of
applicable
procedures
that
implement
the
requirements
of
this
subsection.

4.3.7
Sharp
or
Heavy
Objects
4.3.7.1
Requirements
Sharp
or
heavy
objects
in
the
waste
shall
be
blocked,
braced,
or
suitably
packaged
as
necessary
to
provide
puncture
protection
for
the
payload
containers
packaging
these
objects,
consistent
with
Section
2.7
of
the
CH­
TRAMPAC.

4.3.7.2
Compliance
and
Verification
For
retrievably
stored
waste,
AK
initially
is
used
to
determine
container
contents.
AK
is
confirmed
by
radiography
and/
or
VE
of
the
payload
container
contents
before
certification.
These
activities
are
consistent
with
section
2.7
of
the
CH­
TRAMPAC
and
WMP­
400,
Section
7.1.8.
As
appropriate,
noncompliant
items
are
removed
or
repackaging
of
sharp
or
heavy
objects
is
conducted
in
a
manner
to
preclude
puncturing
the
payload
container.

Refer
to
Appendix
A,
column
"
CH­
WAC
and
Certification
Plan
Section,"
row
3.4.1,
which
contains
the
titles
of
applicable
procedures
that
implement
the
requirements
of
this
subsection.

4.3.8
Sealed
Containers
4.3.8.1
Requirements
Sealed
containers
greater
than
4
liters
are
prohibited,
except
for
waste
material
type
II.
2
packaged
in
metal
containers.
Waste
material
type
II.
2
in
metal
containers
does
not
generate
any
flammable
gas
(
see
subsection
3.4.2
of
this
Certification
Plan
and
Section
2.8
of
the
CHTRAMPAC
A
single,
unvented
heat­
sealed
bag
is
allowed
with
a
minimum
surface
area
of
approximately
390
square
inches
provided
the
requirements
contained
within
Appendix
6.13
of
the
CH­
TRU
Payload
Appendices
are
met.
Heat­
sealed
bag
requirements
are
not
addressed
in
the
CH­
TRAMPAC.

4.3.8.2
Compliance
and
Verification
For
newly
generated
waste,
the
waste
generators
use
the
VE
technique
during
packaging
to
ensure
prohibited
physical
waste
forms
are
not
present
in
waste
containers.
Waste
generators
process
items
such
as
pressurized
or
sealed
containers
to
eliminate
any
condition
that
may
result
HNF­
2600,
REV
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HANFORD
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PLAN
in
rejection
of
the
payload
container.
The
generator
verifies
that
the
waste
placed
in
the
container
meets
the
physical
form
requirements.
Friction­
fit
or
slip­
lid
containers
are
not
considered
to
be
sealed
unless
the
lid
is
completely
taped
around
its
edge
to
the
container
body.
A
rigid
55­
gallon
drum
liner,
if
present,
shall
be
punctured
with
a
hole
with
a
minimum
0.3­
inch
diameter
or
fitted
with
a
filter,
consistent
with
Section
2.5
of
the
CH­
TRAMPAC.
Twist­
andtape
closure,
fold­
and­
tape
closure,
and
heat­
seal
closure
(
with
a
minimum
of
one
filter
vent)
are
allowable
methods
for
closing
plastic
bags
used
for
waste
confinement.
Compliance
with
CH­
TRU
Payload
Appendices
6.13
requirements
shall
be
met
for
the
use
of
a
single,
unvented
heat­
sealed
bag
layer.
For
retrievably
stored
waste,
project
personnel
ensure
compliance
with
the
physical
form
requirements
through
AK
verified
by
radiography
and/
or
VE
of
the
payload
container
contents.
A
payload
container
rejected
for
noncompliance
with
the
physical
form
requirements
is
marked
and
segregated,
or
the
noncompliant
item
is
removed
and
the
container
is
repackaged
and
reprocessed
to
verify
remaining
certification
requirements.
The
TCO
verifies
compliance
on
the
PCTCD
or
OPCTCD
and
the
container
integrity
checklist,
in
accordance
with
WMP­
400,
Section
2.1.5.

Refer
to
Appendix
A,
column
"
CH­
WAC
and
Certification
Plan
Section,"
row
3.4.2,
which
contain
the
titles
of
applicable
procedures
that
implement
the
requirements
of
this
subsection.

4.4
NUCLEAR
PROPERTIES
REQUIREMENTS
4.4.1
Nuclear
Criticality
4.4.1.1
Requirements
A
payload
container
shall
be
acceptable
for
transport
only
if
the
239Pu
fissile
gram
equivalent
(
FGE)
plus
two
times
the
measurement
error
is
less
than
or
equal
to
the
following
limits:

Drums
 
200
grams
for
a
55­
or
85­
gallon
drum,
except
for
drums
containing
greater
than
1%
by
weight
beryllium
(
Be)
or
beryllium
oxide
(
BeO)
 
100
grams
for
a
55­
or
85­
gallon
drum
containing
greater
than
1%
by
weight
Be
or
BeO
SWBs
or
TDOPs
 
325
grams
for
a
SWB
or
TDOP,
except
for
SWBs
or
TDOPs
containing
greater
than
1%
by
Be
or
BeO
 
100
grams
for
a
SWB
or
TDOP
containing
greater
than
1%
by
weight
Be
or
BeO
Pipe
Overpacks
 
200
grams
for
a
standard
pipe
overpack,
S100
pipe
overpack
or
S200
pipe
overpack.
HNF­
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REV
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HANFORD
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PLAN
If
a
payload
container
will
be
overpacked,
FGE
limits
apply
only
to
the
outermost
payload
container
of
the
overpacked
configuration.

A
TRUPACT­
II
shall
be
acceptable
for
transport
only
if
the
239Pu
FGE
plus
two
times
the
measurement
error
is
less
than
or
equal
to
the
following
limits:

No
Credit
for
240Pu
Poisoning
Drums
 
325
grams
for
a
payload
of
55­
or
85­
gallon
drums,
except
for
payloads
containing
greater
than
1%
by
weight
Be
or
BeO.
 
100
grams
for
a
payload
of
55­
or
85­
gallon
drums
containing
greater
than
1%
by
weight
Be
or
BeO
SWBs
and
TDOPs
 
325
grams
for
a
payload
of
SWB(
s)
or
a
TDOP,
except
for
payloads
containing
greater
than
1%
by
weight
Be
or
BeO
 
100
grams
for
a
payload
of
SWB(
s)
or
a
TDOP
containing
greater
than
1%
by
weight
Be
or
BeO
Pipe
Overpacks
 
2800
grams
per
TRUPACT­
II
for
a
payload
of
standard
pipe
overpacks,
S100
pipe
overpacks
or
S200
pipe
overpacks.

A
payload
composed
of
both
55­
gallon
drums
and
standard
pipe
overpack
payload
containers
shall
be
acceptable
for
transport
only
if
the
239Pu
FGE
plus
two
times
the
measurement
error
(
i.
e.,
two
standard
deviations)
is
less
than
or
equal
to
the
applicable
55­
gallon
drum
payload
limit.

Table
4.4­
1
presents
a
summary
of
the
FGE
limits
for
payload
containers
and
payloads.

Credit
for
240Pu
Poisoning
 
For
payloads
of
55­
or
85­
gallon
drums,
or
SWB(
s)
containing
less
than
or
equal
to
1%
by
weight
Be
or
BeO
the
package
limits
specified
in
Table
4.4­
1
apply.
The
minimum
240Pu
content
for
the
payload
shall
be
determined
after
subtraction
of
two
times
the
error.
HNF­
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HANFORD
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Table
4.4­
1
Summary
of
FGE
Limits
FGE
Limits
with
No
Credit
for
240Pu
Poisoning
Contents
Payload
Container
Fissile
Limit
for
Payload
Container
(
239Pu
FGE)
a
Fissile
Limit
per
TRUPACT­
II
Package
(
239Pu­
FGE)
Drum
200
325
Pipe
Overpack
200
2800
SWB
325
325
Not
machine
compacted
with
 
1
%
by
weight
Be/
BeO
TDOP
325
325
Drum
100
100
Pipe
Overpack
200
2800
SWB
100
100
Not
machine
compacted
with
>
1
%
by
weight
Be/
BeO
TDOP
100
100
FGE
Limits
with
Credit
for
240Pu
Poisoning
Contents
Minimum
240Pu
Content
in
Payload
(
grams)
Fissile
Material
Limit
per
Package
(
239Pu
FGE)
5
340
15
360
Not
machine
compacted
with
 
1
%
by
weight
Be/
BeO
in
drums
or
SWB(
s)
25
380
aThe
FGE
limit
given
applies
to
the
payload
container
regardless
of
240Pu
content
in
package.

There
are
two
primary
methods
for
determining
isotopic
composition
(
3.1.2
of
CH­
TRAMPAC).
Mass
spectrometry
(
MS)
is
a
primary
method
for
determining
radioisotopic
composition
of
plutonium
product
material.
Gamma
ray
pulse
height
analysis
is
the
other
method
used
to
determine
isotopic
composition
for
gamma­
emitting
radionuclides.
When
MS
is
used
to
determine
isotopic
composition,
the
analyses
must
be
performed
in
accordance
with
American
Society
for
Testing
and
Materials
(
ASTM)
methods
(
e.
g.,
ASTM
C
696­
80,
ASTM
C
697­
86,
and
ASTM
C
759­
79
or
equivalent.
NDA
is
performed
in
accordance
with
Appendix
E
of
this
Certification
Plan
and
is
consistent
with
section
3.1.2
of
the
CH­
TRAMPAC.

The
following
are
the
five
allowed
assay
methods
for
quantifying
radionuclides
in
TRU
waste.
These
methods
are
described
in
Section
3.1.2
of
the
CH­
TRAMPAC.

1.
Passive
gamma
2.
Radiochemical
3.
Passive
neutron
coincidence
counting
assay
HNF­
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HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
4.
Passive­
active
neutron
assay
5.
Calorimetry.

239Pu
FGE
for
other
fissile
or
fissionable
isotopes,
including
special
actinide
elements,
shall
be
obtained
using
the
American
National
Standards
Institute,
American
Nuclear
Society
method
ANSI/
ANS­
8.15­
1981,
or
an
equivalent
method.
Table
3­
1­
2
of
the
CH­
TRAMPAC
lists
the
239Pu
FGE,
as
well
as
the
decay
heat
and
specific
activity
of
many
radionuclides.

The
quantity
of
the
radionuclides
in
each
payload
container
shall
be
estimated
by
either
a
direct
measurement
or
records
of
the
individual
payload
container,
summation
of
assay
results
from
individual
packages
in
a
payload
container,
or
by
direct
measurement
on
a
representative
sample
of
a
waste
stream.
The
measured
quantity
of
radiation
is
used
to
calculate
the
quantity
of
other
radionuclides
and
the
total
quantity
of
239Pu
FGE.

The
isotopic
inventory
for
each
payload
container
shall
include
the
identity,
total
quantity,
and
measurement
error
for
all
radionuclides
in
the
waste
container.
In
addition,
the
total
fissile
loading
in
239Pu
FGE
and
its
measurement
error
must
be
determined
for
each
payload
container.
The
239Pu
FGE
for
each
payload
container
is
summed
to
compute
the
total
measured
239Pu
FGE
for
the
proposed
TRUPACT­
II
payload.
The
total
239Pu
FGE
error
is
the
square
root
of
the
sum
of
the
squares
of
the
individual
239Pu
FGE
errors.
The
total
shipment
239Pu
FGE
(
measured
value
plus
two
times
the
total
error)
is
compared
to
the
TRUPACT­
II
limit
for
239Pu
FGE.

4.4.1.2
Compliance
and
Verification
Project
personnel
compile
and
review
AK
to
make
initial
determinations
about
radionuclide
content
and
concentrations.
NDA
personnel
at
WRAP
confirm
AK
by
obtaining
information
on
the
isotopic
composition
of
the
waste
through
radioassay
of
the
filled
payload
container
following
WRP1­
OP­
0906,
WRP1­
OP­
0907,
or
TRU­
OP­
002,
and,
if
necessary,
WRP1­
OP­
0905.
NDA
personnel
at
PFP
confirm
AK
by
obtaining
information
on
the
isotopic
composition
of
the
waste
through
radioassay
of
the
storage
cans
that
are
packaged
into
the
payload
container
following
ZA­
948­
392,
or
ZA­
948­
393.
The
NDA
requirements
are
specified
in
Appendix
E
of
this
certification
plan.

NDA
personnel
compute
the
container
239Pu
FGE
and
container
239Pu
FGE
error
manually
or
using
a
computational
algorithm.
Individual
radionuclide
mass
quantities
and
errors
are
converted
to
239Pu
FGE
by
multiplying
the
mass
values
(
g)
by
239Pu
FGE
conversion
factors
(
FGE/
g)
listed
in
the
CH­
TRAMPAC.
The
container
239Pu
FGE
is
determined
by
summing
the
239Pu
FGE
for
each
radionuclide
in
the
container.

The
TCO
verifies
the
container
FGE
data
and
prints
PCTCD
or
OPCTCD
from
WWIS,
in
accordance
with
WMP­
400,
Section
2.1.5.
The
TCO
uses
the
WWIS
PCTCD
or
OPCTCD
and
compares
the
result
to
the
limits
of
200
FGE
per
drum
or
pipe
overpack
and
325
FGE
per
SWB,
or
TDOP.
If
the
container
does
not
meet
the
criterion,
project
personnel
at
WRAP
repackage
it
in
accordance
with
WRP1­
OP­
0725,
"
TRU
Sorting
Glovebox
Operation."
HNF­
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2005
HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
To
assess
compliance
with
the
payload
239Pu
FGE
requirements,
the
TCO
prints
the
PATCD
from
WWIS
and
verifies
requirements
are
met.
The
payload
239Pu
FGE
is
computed
as
the
sum
of
the
container
239Pu
FGE
values
for
all
containers
in
the
proposed
payload.
The
payload
239Pu
FGE
error
is
computed
by
taking
the
square
root
of
the
sum
of
the
squares
of
two
times
the
container
239Pu
FGE
error
values
for
all
containers
in
the
payload.
Finally,
the
payload
239Pu
FGE
and
the
payload
239Pu
FGE
error
are
summed
and
compared
to
the
limit
of
325
239Pu
FGE
or
2800
239Pu
FGE
per
14
POCs.
The
239Pu
FGE
and
its
associated
measurement
error
are
reported
to
WWIS
consistent
with
WMP­
400,
Section
7.1.5.
If
the
payload
does
not
meet
the
criterion,
a
different
combination
of
payload
containers
is
identified
that
meets
the
TRUPACT­
II
239Pu
FGE
limit.

Refer
to
Appendix
A,
column
"
CH­
WAC
and
Certification
Plan
Section,"
rows
3.3.1
and
3.3.2,
which
contain
the
titles
of
applicable
procedures
that
implement
the
requirements
of
this
subsection.

4.4.2
Radiation
Dose
Rates
4.4.2.1
Requirements
The
external
radiation
dose
rates
of
individual
payload
containers
and
the
loaded
TRUPACT­
II
payloads
to
be
shipped
on
a
trailer
must
be
less
than
or
equal
to
the
limits
specified
in
Table
4.4­
2
below.

Table
4.4­
2
Maximum
Surface
Dose
Rate
Limits
Payload
Container
Maximum
Surface
Dose
(
mrem/
hr)
55­
Gallon
Drum
200
Standard
Pipe
Overpack
200
S100
Pipe
Overpack
179
S200
Pipe
Overpack
200
85­
Gallon
Drum
200
SWB
200
TDOP
200
Source:
Subsection
3.2,
Table
3.2­
1,
of
the
CH­
TRAMPAC
The
radiation
dose
rates
for
the
TRUPACT­
II
must
also
comply
with
10
CFR
71.47.
Drums
that
exceed
the
200­
mrem/
hr
surface
dose
rate
may
not
be
transported
in
a
TRUPACT­
II.
Internal
payload
container
shielding
shall
not
be
used
to
meet
dose
rate
limits
( 
200
mrem/
hr)
except
for
the
POC
configurations
shown
in
Section
2.9
of
the
CH­
TRAMPAC.

In
addition,
S100,
and
S200
pipe
overpacks
shall
meet
the
curie
limits
identified
in
Section
4.4.3.
HNF­
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HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
4.4.2.2
Compliance
and
Verification
A
Hanford
site
RCT
measures
surface
dose
rates
of
the
individual
payload
containers
in
accordance
with
WRP1­
OP­
1225
using
the
beta­
gamma
and
neutron
dose
rates
for
each
container
at
the
surface,
and
records
the
results
for
each
payload
container.
If
the
combined
betagamma
and
neutron
dose
rate
exceeds
200
mrem/
hr
at
the
surface,
the
container
is
rejected,
marked,
and
segregated.
Corrective
action
is
taken
to
resolve
the
noncompliant
condition.
In
addition,
S100,
and
S200
pipe
overpacks
shall
meet
the
curie
limits
identified
in
Section
2.9
of
the
CH­
TRAMPAC,
respectively.
The
payload
container
and
the
TRUPACT­
II
surface
dose
rate
and
the
dose
rate
at
2
meters
shall
be
measured
with
instruments
traceable
to
a
national
standard.
The
dose
rates
shall
be
recorded
before
each
shipment.

The
RCT
also
surveys
the
loaded
TRUPACT­
II
surface
before
shipping.
Additionally,
the
reading
from
a
TRUPACT­
II
at
a
2­
meter
distance
from
any
side
of
the
TRUPACT­
II
(
excluding
the
top
and
bottom)
is
entered
into
WWIS.
If
this
reading
exceeds
10
mrem/
hr
at
2
meters,
the
TCO
rejects
the
TRUPACT­
II
from
shipment.
If
the
TRUPACT­
II
is
rejected
from
shipment,
corrective
action
is
taken
to
resolve
the
noncompliant
condition.

After
the
payload
assemblies
are
loaded
into
the
TRUPACT­
II
and
the
transport
vehicle
(
tractor)
is
connected
to
the
trailer,
the
RCT
surveys
the
vehicle's
driver
and
passenger
space
to
ensure
the
dose
rate
does
not
exceed
2
mrem/
hr.
The
TCO
reviews
the
radiation
dose
rates
and
enters
the
results
of
the
RCT
survey
of
the
TRUPACT­
II
and
transport
vehicle
in
WWIS
for
the
payload
assembly,
consistent
with
WMP­
400,
Section
2.1.5.
Dose
rates
for
payload
containers
and
TRUPACT­
II
vessels
are
reported
to
WWIS
consistent
with
WMP­
400,
Section
7.1.5.
Project
personnel
submit
radiation
dose
rate
measurement
reports
to
the
project
records
custodian.
The
TCO
verifies
compliance
with
the
radiation
dose
rate
requirements
by
signing
the
PATCD
in
accordance
with
WMP­
400,
Section
2.1.5.

Refer
to
Appendix
A,
column
"
CH­
WAC
and
Certification
Plan
Section,"
row
3.3.6,
which
contains
the
titles
of
applicable
procedures
that
implement
the
requirements
of
this
subsection.

4.4.3
Activity
Limits
4.4.3.1
Requirements
The
TRUPACT­
II
is
limited
to
a
maximum
total
activity
of
406
curies
(
Ci)
when
packaging
payloads
of
S100
pipe
overpacks.
The
S100
pipe
overpack
payloads
are
limited
to
sealed
neutron
sources
in
the
forms
specified
in
Table
4.4­
3
below.
Each
payload
shall
be
acceptable
for
shipment
only
if
the
determined
activity
plus
the
error
(
i.
e.,
one
standard
deviation)
meets
this
limit.
HNF­
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HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
Table
4.4­
3
Sealed
Source
Forms
for
S100
Pipe
Overpacks
241Am
Be
238Pu
O
239Pu
Li
241Am
238Pu
Be
239Pu
O
238Pu
B
238Pu
239Pu
Be
244Cm
O
239Pu
F
239Pu
241Am
O
241Am
Li
238Pu
13C
244Cm
The
contents
of
each
S200
pipe
overpack
are
limited
to
the
radionuclides
and
associated
activities
listed
in
Table
4.4­
4
below
for
both
the
S200­
A
and
S200­
B
shield
insert
configurations.
Each
S200
pipe
overpack
shall
be
acceptable
for
shipment
only
if
the
determined
activity
plus
the
error
(
i.
e.,
one
standard
deviation)
meets
the
applicable
limit.

No
activity
limits
exist
for
55­
gallon
drums,
standard
pipe
overpacks,
85­
gallon
drums,
,
SWBs,
or
TDOPs.

4.4.3.2
Compliance
and
Verification
Compliance
with
the
activity
requirements
is
similar
to
the
compliance
methodology
described
in
Section
4.4.1.2.

The
total
activity
plus
the
error
(
i.
e.,
one
standard
deviation)
for
a
payload
of
S100
pipe
overpacks
shall
be
calculated
and
compared
to
the
limit
(
406
Ci).

For
each
S200
pipe
overpack,
the
sum
of
"
partial
fractions"
for
any
combination
of
radionuclides
present
in
the
waste
must
be
less
than
or
equal
to
one.
The
limits
for
individual
radionuclides
are
specified
in
Table
4.4­
4
below.

No
activity
limits
exist
for
55­
gallon
drums,
standard
pipe
overpacks,
85­
gallon
drums,
SWBs,
or
TDOPs.

WMP­
400,
Sections
2.1.5
and
7.1.8,
implements
this
subsection.

Table
4.4­
4
Limiting
Activity
per
S200
Pipe
Overpack
Radionuclide
Name
S200­
A
Limiting
Activity
(
Ci)
S200­
B
Limiting
Activity
(
Ci)
Radionuclide
Name
S200­
A
Limiting
Activity
(
Ci)
S200­
B
Limiting
Activity
(
Ci)
3H
unlimited
unlimited
103Ru
6.524E­
01
1.750E­
01
14C
unlimited
unlimited
106Ru
unlimited
unlimited
22Na
3.722E­
02
2.343E­
02
103mRh
1.618E+
05
1.618E+
05
32P
unlimited
unlimited
106Rh
6.710E­
01
2.764E­
01
51Cr
1.226E+
01
1.226E+
01
107Pd
unlimited
unlimited
54Mn
8.440E­
02
4.331E­
02
109mAg
2.974E+
03
2.974E+
03
55Fe
unlimited
unlimited
110Ag
3.900E+
00
1.594E+
00
59Fe
4.192E­
02
2.577E­
02
110mAg
2.521E­
02
1.351E­
02
HNF­
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HANFORD
SITE
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WASTE
CERTIFICATION
PLAN
Radionuclide
Name
S200­
A
Limiting
Activity
(
Ci)
S200­
B
Limiting
Activity
(
Ci)
Radionuclide
Name
S200­
A
Limiting
Activity
(
Ci)
S200­
B
Limiting
Activity
(
Ci)
57Co
2.641E+
01
2.641E+
01
109Cd
2.974E+
03
2.974E+
03
58Co
8.829E­
02
4.471E­
02
113mCd
7.540E+
03
7.540E+
03
60Co
1.906E­
02
1.195E­
02
119mSn
6.826E+
02
6.826E+
02
59Ni
unlimited
unlimited
121mSn
5.948E+
03
5.948E+
03
63Ni
unlimited
unlimited
123Sn
7.589E+
00
4.521E+
00
64Cu
7.156E+
00
4.600E+
00
126Sn
1.726E+
02
1.726E+
02
65Zn
9.129E­
02
5.486E­
02
125Sb
5.782E­
01
1.908E­
01
73As
1.055E+
03
1.055E+
03
126Sb
4.239E­
02
1.826E­
02
79Se
unlimited
unlimited
126mSb
9.044E­
02
3.658E­
02
85Kr
1.363E+
02
3.709E+
01
123Te
unlimited
unlimited
86Rb
5.643E­
01
3.353E­
01
123mTe
7.703E+
00
7.703E+
00
89Sr
7.224E+
02
3.920E+
02
125mTe
1.542E+
03
1.542E+
03
90Sr
unlimited
unlimited
127Te
7.613E+
01
4.597E+
01
88Y
1.709E­
02
1.110E­
02
127mTe
1.323E+
03
5.207E+
02
90Y
1.328E+
06
9.330E+
05
125I
1.647E+
03
1.647E+
03
90mY
6.476E­
01
2.442E­
01
129I
1.465E+
03
1.465E+
03
91Y
1.572E+
01
9.695E+
00
131I
9.832E­
01
5.754E­
01
88Zr
9.496E­
01
7.384E­
01
134Cs
6.216E­
02
2.832E­
02
90Zr
unlimited
unlimited
135Cs
unlimited
unlimited
90mZr
unlimited
unlimited
137Cs
2.181E­
01
8.747E­
02
93Zr
1.975E+
07
1.975E+
07
133Ba
1.142E+
00
1.142E+
00
95Zr
1.248E­
01
5.705E­
02
137Ba
unlimited
unlimited
95Nb
1.100E­
01
5.212E­
02
137mBa
2.060E­
01
8.261E­
02
95mNb
8.103E+
00
8.103E+
00
141Ce
2.011E+
01
2.011E+
01
99Tc
1.693E+
07
1.693E+
07
144Ce
1.539E+
02
1.539E+
02
99mTc
1.385E+
01
1.385E+
01
144Pr
1.779E+
00
1.126E+
00
144mPr
5.304E+
01
3.512E+
01
214Po
unlimited
unlimited
146Pm
1.958E­
01
8.003E­
02
215Po
2.053E+
03
9.111E+
02
147Pm
1.175E+
06
1.175E+
06
216Po
4.824E+
03
2.419E+
03
146Sm
unlimited
unlimited
218Po
unlimited
unlimited
147Sm
unlimited
unlimited
211At
6.139E+
01
2.565E+
01
151Sm
3.504E+
05
3.504E+
05
217At
1.968E+
03
8.069E+
02
150Eu
1.001E­
01
4.605E­
02
219Rn
7.163E+
00
7.163E+
00
152Eu
5.488E­
02
3.263E­
02
220Rn
3.632E+
02
1.115E+
02
154Eu
4.915E­
02
2.843E­
02
222Rn
8.103E+
02
2.176E+
02
155Eu
1.743E+
02
1.743E+
02
221Fr
2.066E+
01
2.066E+
01
HNF­
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REV
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88
of
281
5/
11/
2005
HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
Radionuclide
Name
S200­
A
Limiting
Activity
(
Ci)
S200­
B
Limiting
Activity
(
Ci)
Radionuclide
Name
S200­
A
Limiting
Activity
(
Ci)
S200­
B
Limiting
Activity
(
Ci)
152Gd
unlimited
unlimited
223Fr
1.078E+
01
5.211E+
00
153Gd
1.898E+
02
1.898E+
02
223Ra
5.380E+
00
5.380E+
00
168Tm
8.380E­
02
4.045E­
02
224Ra
5.031E+
01
5.031E+
01
182Ta
4.298E­
02
2.631E­
02
225Ra
3.668E+
02
3.668E+
02
198Au
9.004E­
01
4.886E­
01
226Ra
1.065E+
02
1.065E+
02
207Tl
2.733E+
01
1.469E+
01
228Ra
5.749E+
03
5.749E+
03
208Tl
1.497E­
02
9.959E­
03
225Ac
8.245E+
01
7.320E+
01
209Tl
2.596E­
02
1.678E­
02
227Ac
3.927E+
04
3.927E+
04
209Pb
unlimited
unlimited
228Ac
7.672E­
02
4.385E­
02
210Pb
2.589E+
03
2.589E+
03
227Th
4.786E+
00
4.786E+
00
211Pb
1.786E+
00
8.441E­
01
228Th
7.082E+
02
7.082E+
02
212Pb
4.342E+
00
4.342E+
00
229Th
2.522E+
01
2.522E+
01
214Pb
1.681E+
00
1.589E+
00
230Th
1.352E+
03
1.336E+
03
207Bi
4.786E­
02
2.598E­
02
231Th
2.833E+
02
2.833E+
02
210Bi
unlimited
unlimited
232Th
2.841E+
03
2.809E+
03
211Bi
8.296E+
00
8.296E+
00
234Th
9.901E+
02
9.901E+
02
212Bi
6.418E­
01
3.564E­
01
231Pa
1.330E+
01
1.330E+
01
213Bi
2.920E+
00
1.052E+
00
233Pa
2.262E+
00
2.262E+
00
214Bi
3.569E­
02
2.213E­
02
234Pa
5.300E­
02
2.859E­
02
209Po
1.519E+
01
8.164E+
00
234mPa
3.751E+
00
2.161E+
00
210Po
7.613E+
03
3.813E+
03
232U
8.615E+
02
8.463E+
02
211Po
1.055E+
01
5.124E+
00
233U
1.179E+
03
1.130E+
03
212Po
unlimited
unlimited
234U
1.202E+
03
1.185E+
03
213Po
2.147E+
03
1.038E+
03
235U
5.003E+
00
5.003E+
00
236U
1.301E+
03
1.286E+
03
245Am
2.809E+
01
2.809E+
01
237U
1.002E+
01
1.002E+
01
240Cm
1.241E+
02
1.227E+
02
238U
1.459E+
01
1.443E+
01
242Cm
7.823E+
01
7.722E+
01
239U
8.798E+
00
4.327E+
00
243Cm
6.475E+
00
6.475E+
00
240U
7.356E+
02
7.356E+
02
244Cm
4.356E+
00
4.306E+
00
237Np
1.416E+
02
1.416E+
02
245Cm
2.649E+
01
2.619E+
01
238Np
8.656E­
02
4.996E­
02
246Cm
1.885E­
02
1.864E­
02
239Np
5.101E+
00
5.101E+
00
247Cm
1.175E+
00
7.922E­
01
240Np
8.373E­
02
4.282E­
02
248Cm
6.126E­
05
6.057E­
05
240mNp
3.198E­
01
1.524E­
01
250Cm
7.043E­
06
6.963E­
06
236Pu
5.764E+
02
5.597E+
02
247Bk
5.606E+
00
5.606E+
00
238Pu
6.171E+
02
6.087E+
02
249Bk
5.710E+
03
5.644E+
03
HNF­
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HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
Radionuclide
Name
S200­
A
Limiting
Activity
(
Ci)
S200­
B
Limiting
Activity
(
Ci)
Radionuclide
Name
S200­
A
Limiting
Activity
(
Ci)
S200­
B
Limiting
Activity
(
Ci)
239Pu
9.319E+
02
8.655E+
02
250Bk
6.133E­
02
3.558E­
02
240Pu
1.158E+
02
1.145E+
02
249Cf
1.175E+
00
1.175E+
00
241Pu
3.874E+
06
3.874E+
06
250Cf
5.989E­
03
5.921E­
03
242Pu
1.334E+
00
1.318E+
00
251Cf
1.237E+
01
1.237E+
01
243Pu
9.208E+
01
9.208E+
01
252Cf
1.548E­
04
1.530E­
04
244Pu
5.548E­
03
5.485E­
03
254Cf
4.781E­
06
4.727E­
06
241Am
2.788E+
02
2.788E+
02
252Es
4.418E­
01
2.180E­
01
242Am
7.973E+
05
7.973E+
05
253Es
4.677E+
01
4.453E+
01
242mAm
1.095E+
02
1.095E+
02
254Es
3.681E+
01
3.681E+
01
243Am
1.409E+
02
1.409E+
02
254mEs
9.086E­
03
8.561E­
03
Note:
The
designation
of
"
unlimited"
is
made
for
any
radionuclide
whose
limiting
activity
is
greater
than
1x108
curies
(
Ci).

4.5
CHEMICAL
PROPERTIES
REQUIREMENTS
4.5.1
Pyrophorics
4.5.1.1
Requirements
A
pyrophoric
is
any
solid
material,
other
than
one
classed
as
an
explosive,
which
under
normal
conditions
is
liable
to
cause
fires
through
friction,
retained
heat
from
manufacturing
or
processing,
or
which
can
be
ignited
readily
and
when
ignited,
burns
so
vigorously
and
persistently
as
to
create
a
serious
transportation
handling
or
disposal
hazard.
Included
are
spontaneously
combustible
and
water­
reactive
materials.

Pyrophoric
radioactive
materials
shall
be
present
only
in
small
residual
amounts
(<
1
percent
[
weight])
in
payload
containers.
Radioactive
pyrophorics
in
concentrations
greater
than
1
percent
by
weight
and
all
nonradioactive
pyrophorics
shall
be
reacted
(
or
oxidized)
and/
or
otherwise
rendered
nonreactive
before
placement
in
the
payload
container.

Refer
to
Appendix
A,
column
"
CH­
WAC
and
Certification
Plan
Section,"
row
3.5.1,
which
contains
the
titles
of
applicable
procedures
that
implement
the
requirements
of
this
subsection.

4.5.1.2
Compliance
and
Verification
Nonradionuclide
pyrophoric
materials
at
the
Hanford
site
are
subject
to
procurement
controls.
In
general,
the
Hanford
site
does
not
permit
pyrophoric
materials
in
TRU
waste
process
areas.
If
a
process
requires
the
use
of
pyrophoric
materials,
the
quantity
of
pyrophoric
materials
that
enters
the
process
is
limited
and
controlled,
and
the
waste
must
be
treated
to
render
it
chemically
safe
before
placement
in
a
waste
container.
HNF­
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HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
Examples
of
pyrophoric
radionuclides
are
metallic
plutonium
and
americium.
Examples
of
nonpyrophoric
are
organic
peroxides,
sodium
metal,
and
chlorates.

For
newly
generated
waste,
waste
generators
use
AK
and
the
VE
technique
during
packaging
to
ensure
prohibited
items
are
not
present
in
waste
containers.
Waste
generators
process
items
to
eliminate
any
condition
that
may
result
in
rejection
of
the
payload
container.
VE
personnel
verify
that
the
waste
placed
in
the
container
meets
the
pyrophoric
restriction.
For
retrievably
stored
waste,
project
personnel
verify
compliance
with
the
pyrophorics
restriction
by
obtaining
information
(
e.
g.,
administrative,
operating,
and
QA
procedures
and
safety
assessments)
documenting
that
waste
does
not
contain
pyrophorics
or
other
prohibited
materials.
Project
personnel
review
and
evaluate
AK
to
verify
that
waste­
producing
processes
included
no
pyrophorics
or
other
prohibited
materials.
AK
includes
sampling
and
analysis
data,
documentation
of
waste
stream
descriptions,
or
actions
to
treat
or
stabilize
the
waste
to
eliminate
specific
characteristics.
Project
personnel
verify
AK
through
radiography
and
VE
of
randomly
selected
waste
containers.
The
TCO
documents
compliance
on
the
PCTCD
or
OPCTCD,
and
the
TCO
and
WCO
confirm
the
pyrophorics
criteria
in
accordance
with
WMP­
400,
Sections
2.1.5
and
7.1.8
respectively.

Refer
to
Appendix
A,
column
"
CH­
WAC
and
Certification
Plan
Section,"
row
3.5.1,
which
contains
the
titles
of
applicable
procedures
that
implement
the
requirements
of
this
subsection.

4.5.2
Explosives,
Corrosives,
and
Compressed
Gases
4.5.2.1
Requirements
An
explosive
is
defined
as
"
Any
substance
or
article,
including
a
device,
which
is
designed
to
function
by
explosion
(
i.
e.,
an
extremely
rapid
release
of
gas
and
heat)
or
which,
by
chemical
reaction
within
itself,
is
able
to
function
in
a
similar
manner."
Examples
of
explosives
are
ammunition,
dynamite,
black
powder,
detonators,
nitroglycerin,
urea
nitrate,
and
picric
acid.

A
corrosive
is
defined
as
an
aqueous
material
that
has
a
pH
less
than
or
equal
to
2
or
greater
than
or
equal
to
12.5.

Explosives,
corrosives,
and
compressed
gases
(
pressurized
containers)
are
prohibited
from
the
payload,
consistent
with
section
4.2
of
the
CH­
TRAMPAC.

4.5.2.2
Compliance
and
Verification
The
Hanford
site
prohibits
explosives,
compressed
gases,
and
corrosive
liquids
in
payload
containers.
Chemicals
(
e.
g.,
oxidizers)
capable
of
forming
explosive
mixtures
under
conditions
incident
to
transportation
or
storage
are
also
prohibited
from
the
waste.
The
Hanford
site
administratively
controls
and
monitors
the
procurement,
distribution,
use,
and
disposal
of
explosive
materials
through
site­
specific
operating
and
QA
procedures.
Additionally,
wastegenerating
processes
must
be
assessed
for
safety
hazards
such
as
potential
explosion
hazards
and
potential
inadvertent
production
of
explosive
materials.
Corrosives
must
be
either
excluded
from
the
payload
container
or
processed
to
neutralize
the
corrosive
material
or
otherwise
render
it
noncorrosive.
Process­
specific
operating
procedures
describe
the
specific
actions
taken
to
ensure
HNF­
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HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
compliance
with
the
corrosive
material
prohibition,
consistent
with
section
4.2
of
the
CH­
TRAMPAC.

Used
(
i.
e.,
empty)
aerosol
cans
are
allowed
as
they
do
not
impact
the
package
internal
pressure
or
flammability.
Verification
that
any
aerosol
can
present
in
retrievably
stored
waste
are
empty
shall
be
by
radiography
and/
or
process
knowledge
and
shall
be
documented
in
site­
specific
compliance
documents.
Any
aerosol
cans
that
are
not
empty
are
prohibited.

For
newly
generated
waste,
waste
generators
use
AK
and
the
VE
technique
during
packaging
to
ensure
that
there
is
no
indication
of
the
presence
of
waste
materials
that
may
contain
explosives,
compressed
gases,
and
corrosives
in
waste
containers.
Waste
generators
process
items
to
eliminate
any
condition
that
may
result
in
rejection
of
the
payload
container.
For
retrievably
stored
waste,
project
personnel
verify
compliance
with
the
prohibited
items
requirement
by
obtaining
information
(
e.
g.,
administrative,
operating,
and
QA
procedures
and
safety
assessments)
documenting
that
waste
does
not
contain
explosives,
corrosives,
or
pressurized
containers.
Project
personnel
review
and
evaluate
AK
to
verify
that
waste­
producing
processes
included
no
prohibited
or
restricted
materials.
AK
includes
sampling
and
analysis
data,
documentation
of
waste
stream
descriptions,
or
actions
to
treat
or
stabilize
the
waste
to
eliminate
specific
characteristics.
Project
personnel
verify
that
prohibited
materials
are
not
in
the
waste
container
through
radiography.
Radiography
is
verified
through
VE
of
randomly
selected
waste
containers.
The
TCO
documents
compliance
on
the
PCTCD
or
OPCTCD,
and
the
TCO
and
WCO
verify
this
information
in
accordance
with
WMP­
400,
Sections
2.1.5
and
7.1.8
respectively.

See
also
Appendix
A,
column
"
CH­
WAC
and
Certification
Plan
Section,"
row
3.5.4,
which
contains
the
titles
of
applicable
procedures
that
implement
the
requirements
of
this
subsection.

4.5.3
Chemical
Composition
4.5.3.1
Requirements
The
chemical
constituents
allowed
within
a
given
waste
material
type
are
restricted
so
that
a
conservative
bounding
G­
value
can
be
established
for
the
gas­
generation
potential
in
each
waste
material
type,
consistent
with
section
4.3
of
the
CH­
TRAMPAC.

Chemical
constituents
in
a
payload
shall
conform
to
the
allowable
chemical
lists
in
Tables
4.3­
1
through
4.3­
8of
the
CH­
TRAMPAC.
The
total
quantity
of
the
trace
chemicals/
materials
(
i.
e.,
materials
that
occur
in
the
waste
in
quantities
less
than
1
percent
[
by
weight])
in
any
payload
container
is
restricted
to
less
than
5
percent
(
weight).

4.5.3.2
Compliance
and
Verification
Waste
generators
and/
or
project
personnel
initially
review
AK
information
to
identify
chemical
constituents
in
the
waste.
AK
is
verified
based
on
the
results
of
sampling
and
analysis
activities.
The
TCO
compares
the
payload
container
inventory
with
the
allowable
material/
chemical
lists
in
Tables
4.5­
1
through
4.5­
8.
If
a
content
code
has
not
been
assigned
to
the
waste
in
the
container,
project
personnel
assign
the
appropriate
content
code
based
on
the
waste
stream
characterization
HNF­
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HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
information
as
described
in
the
CH­
TRUCON
document.
If
the
waste
is
not
listed
in
the
correlation
tables
of
the
CH­
TRUCON
document
or
if
there
is
no
corresponding
content
code
listed
in
the
CH­
TRUCON
document,
the
payload
container
is
not
eligible
for
shipment.
The
TCO
requests
content
code
changes
or
additions
from
the
TRU
WIPP
CH­
TRU
Payload
Engineer
as
necessary.
The
TCO
and
WCO
verify
the
content
code
assignment
of
each
payload
container
before
certification
for
shipment
to
WIPP
in
accordance
with
WMP­
400,
Sections
2.1.5
and
7.1.8
respectively.

See
also
Appendix
A,
column
"
CH­
WAC
and
Certification
Plan
Section,"
rows
3.5.3which
contain
the
titles
of
applicable
procedures
that
implement
the
requirements
of
this
subsection.

4.5.4
Chemical
Compatibility
4.5.4.1
Requirements
The
allowable
chemical
lists
in
the
CH­
TRAMPAC
Tables
4.3­
1
through
4.3­
8
restrict
the
chemical
composition
of
the
TRUPACT­
II
payload.
Chemical
compatibility
of
a
waste
with
its
packaging
ensures
that
chemical
processes
will
not
occur
that
might
pose
a
threat
to
the
safe
transport
of
a
payload
in
the
TRUPACT­
II.
Chemical
compatibility
has
been
verified
for
the
following:

 
Chemical
compatibility
of
the
waste
form
within
each
individual
payload
container
 
Chemical
compatibility
between
contents
of
payload
containers
during
hypothetical
accident
conditions
 
Chemical
compatibility
of
waste
forms
within
the
TRUPACT­
II
inner
containment
vessel
(
ICV)
 
Chemical
compatibility
of
the
waste
form
with
the
TRUPACT­
II
O­
ring
seals.

4.5.4.2
Compliance
and
Verification
Project
personnel
ensure
compliance
with
the
chemical
compatibility
requirements
based
on
AK
and
analytical
data,
consistent
with
EPA
guidance
(
EPA­
600/
2­
80­
076,
A
Method
for
Determining
Compatibility
of
hazardous
Wastes).
The
TCO
verifies
chemical
compatibility
by
comparing
payload
container
inventory
with
approved
content
codes
using
the
chemical
lists
in
Tables
4.5­
1
through
4.5­
8
below.
The
TCO
and
WCO
confirm
chemical
compatibility
criteria
in
accordance
with
WMP­
400,
Sections
2.1.5
and
7.1.8
respectively.
If
necessary,
project
personnel
repackage
CH
TRU
waste
containers
not
meeting
the
chemical
compatibility
requirement.

Refer
to
Appendix
A,
column
"
CH­
WAC
and
Certification
Plan
Section,"
row
3.5.3,
which
contains
the
titles
of
applicable
procedures
that
implement
the
requirements
of
this
subsection.
HNF­
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HANFORD
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CERTIFICATION
PLAN
Table
4.5­
1
Allowable
Materials
for
Waste
Material
Type
1.1a
Absorbed,
Adsorbed,
or
Solidified
Inorganic
Liquid
Absorbents/
adsorbents
(
e.
g.,
Celite
®
,
diatomaceous
earth,
diatomite,
Florco
®
,
Oil­
Dri
®
,
perlite,
vermiculite)
Acids,
inorganic
Alumina
cement
Aquaset
®
products
(
for
aqueous
solutions)
Aqueous
sludges
Aqueous
solutions/
water
Asbestos
Ash
(
e.
g.,
ash
bottoms,
fly
ash,
soot)
Batteries,
dry
(
e.
g.,
flashlight)
Ceramics
(
e.
g.,
molds
and
crucibles)
Clays
(
e.
g.,
bentonite)
Concrete
Envirostone
®
(
no
organic
emulsifiers
allowed)
Fiberglass,
inorganic
Filter
media,
inorganic
Firebrick
Glass
(
e.
g.,
borosilicate
glass,
labware,
leaded
glass,
Raschig
rings)
Graphite
(
e.
g.,
molds
and
crucibles)
Grit
Heel
(
e.
g.,
ash
heel;
soot
heel;
firebrick
heel;
sand,
slag,
and
crucible
heel)
Insulation,
inorganic
Magnesia
cement
(
e.
g.,
Ramcote
®
cement)
Metal
hydroxides
Metal
oxides
(
e.
g.,
slag)
Metals
(
e.
g.,
aluminum,
cadmium,
copper,
steel,
tantalum,
tungsten,
zinc)
Nitrates
(
e.
g.,
ammonium
nitrate,
sodium
nitrate)
Petroset
®
products
(
for
aqueous
solutions)
Portland
cement
Sand/
soil,
inorganic
Salts
(
e.
g.,
calcium
chloride,
calcium
fluoride,
sodium
chloride)
Other
inorganic
materials
aOther
chemicals
or
materials
not
identified
in
this
table
are
allowed
provided
that
they
meet
the
requirements
of
Section
4.5.3.
All
materials
in
the
final
waste
form
must
be
inert
(
nonreactive),
be
in
a
nonreactive
form,
or
have
been
rendered
nonreactive.
HNF­
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HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
Table
4.5­
2
Allowable
Materials
for
Waste
Material
Type
I.
2a
Soils,
Solidified
Particulates,
or
Sludges
Formed
from
Precipitation
Absorbents/
adsorbents
(
e.
g.,
Celite
®
,
diatomaceous
earth,
diatomite,
Florco
®
,
Oil­
Dri
®
,
perlite,
vermiculite)
Alumina
cement
Aquaset
®
products
(
for
aqueous
solutions)
Aqueous
sludges
Aqueous
solutions/
water
Asbestos
Ash
(
e.
g.,
ash
bottoms,
fly
ash,
soot)
Batteries,
dry
(
e.
g.,
flashlight)
Ceramics
(
e.
g.,
molds
and
crucibles)
Clays
(
e.
g.,
bentonite)
Concrete
Fiberglass,
inorganic
Filter
media,
inorganic
Firebrick
Glass
(
e.
g.,
borosilicate
glass,
labware,
leaded
glass,
Raschig
rings)
Graphite
(
e.
g.,
molds
and
crucibles)
Grit
Heel
(
e.
g.,
ash
heel;
soot
heel;
firebrick
heel;
sand,
slag,
and
crucible
heel)
Insulation,
inorganic
Magnesia
cement
(
e.
g.,
Ramcote
®
cement)
Metal
hydroxides
Metal
oxides
(
e.
g.,
slag)
Metals
(
e.
g.,
aluminum,
cadmium,
copper,
steel,
tantalum,
tungsten,
zinc)
Nitrates
(
e.
g.,
ammonium
nitrate,
sodium
nitrate)
Petroset
®
products
(
for
aqueous
solutions)
Portland
cement
Sand/
soil,
inorganic
Salts
(
e.
g.,
calcium
chloride,
calcium
fluoride,
sodium
chloride)
Other
inorganic
materials
aOther
chemicals
or
materials
not
identified
in
this
table
are
allowed
provided
that
they
meet
the
requirements
of
Section
4.5.3.
All
materials
in
the
final
waste
form
must
be
inert
(
nonreactive),
be
in
a
nonreactive
form,
or
have
been
rendered
nonreactive.
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HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
Table
4.5­
3
Allowable
Materials
for
Waste
Material
Type
I.
3a
Concreted
Inorganic
Particulate
Waste
Absorbents/
adsorbents
(
e.
g.,
Celite
®
,
diatomaceous
earth,
diatomite,
Florco
®
,
Oil­
Dri
®
,
perlite,
vermiculite)
Asbestos
Ash
(
e.
g.,
ash
bottoms,
fly
ash,
soot)
Batteries,
dry
(
e.
g.,
flashlight)
Ceramics
(
e.
g.,
molds
and
crucibles)
Clays
(
e.
g.,
bentonite)
Concrete
Fiberglass,
inorganic
Filter
media,
inorganic
Firebrick
Glass
(
e.
g.,
borosilicate
glass,
labware,
leaded
glass,
Raschig
rings)
Graphite
(
e.
g.,
molds
and
crucibles)
Grit
Heel
(
e.
g.,
ash
heel;
soot
heel;
firebrick
heel;
sand,
slag,
and
crucible
heel)
Insulation,
inorganic
Metal
hydroxides
Metal
oxides
(
e.
g.,
slag)
Metals
(
e.
g.,
aluminum,
cadmium,
copper,
steel,
tantalum,
tungsten,
zinc)
Nitrates
(
e.
g.,
ammonium
nitrate,
sodium
nitrate)
Portland
cement
Sand/
soil,
inorganic
Salts
(
e.
g.,
calcium
chloride,
calcium
fluoride,
sodium
chloride)
Water
(
maximum
of
30
weight
percent
unbound
water)
Other
inorganic
materials
aOther
chemicals
or
materials
not
identified
in
this
table
are
allowed
provided
that
they
meet
the
requirements
of
Section
4.5.3.
All
materials
in
the
final
waste
form
must
be
inert
(
nonreactive),
be
in
a
nonreactive
form,
or
have
been
rendered
nonreactive.
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HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
Table
4.5­
4
Allowable
Materials
for
Waste
Material
Types
II.
1
and
II.
2a
Solid
Inorganic
Materials
Absorbents/
adsorbents
(
e.
g.,
Celite
®
,
Florco
®
,
Oil­
Dri
®
,
diatomite,
perlite,
vermiculite)
b
Asbestos
Ash
(
e.
g.,
ash
bottoms,
fly
ash,
soot)
Batteries,
dry
(
e.
g.,
flashlight)
Ceramics
(
e.
g.,
molds
and
crucibles)
Clays
(
e.
g.,
bentonite)
Concrete/
Portland
cement
(
surface
contaminated
only)
Fiberglass,
inorganic
Filter
media,
inorganic
Firebrick
Glass
(
e.
g.,
borosilicate
glass,
labware,
leaded
glass,
Raschig
rings)
Graphite
(
e.
g.,
molds
and
crucibles)
Grit
Heel
(
e.
g.,
ash
heel;
soot
heel;
firebrick
heel;
sand,
slag,
and
crucible
heel)
Insulation,
inorganic
Magnesium
alloy
Metal
oxides
(
e.
g.,
slag)
Metals
(
e.
g.,
aluminum,
cadmium,
copper,
steel,
tantalum,
tungsten,
zinc)
Nitrates
(
e.
g.,
ammonium
nitrate,
sodium
nitrate)
Salts
(
e.
g.,
calcium
chloride,
calcium
fluoride,
sodium
chloride)
Sand/
soil,
inorganic
Other
inorganic
materials
aOther
chemicals
or
materials
not
identified
in
this
table
are
allowed
provided
that
they
meet
the
requirements
of
Section
4.5.3.
All
materials
in
the
final
waste
form
must
be
inert
(
nonreactive),
be
in
a
nonreactive
form,
or
have
been
rendered
nonreactive.
bDry
absorbents/
adsorbents
and
other
dry
desiccants
are
allowed
if
they
contain
no
absorbed
or
adsorbed
liquids.

Table
4.5­
5
­
Allowable
Materials
for
Waste
Material
Type
II.
3a
Homogeneous
Solid
Inorganic
Materials
with
Unbound
Absorbed
Ambient
Moisture
( 
6%
by
weight)

Any
material
in
Waste
Material
Types
II.
1
and
II.
2
(
Table
4.5­
4)
and
water
as
unbound
absorbed
ambient
moisture
( 
6%
by
weight).
aOther
chemicals
or
materials
not
identified
in
this
table
are
allowed
provided
that
they
meet
the
requirements
of
Section
4.5.3.
All
materials
in
the
final
waste
form
must
be
inert
(
nonreactive),
be
in
a
nonreactive
form,
or
have
been
rendered
nonreactive.
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HANFORD
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TRANSURANIC
WASTE
CERTIFICATION
PLAN
Table
4.5­
6
Allowable
Materials
for
Waste
Material
Type
III.
1a
Solid
Organic
Materials
Any
material
in
Waste
Types
I
or
II
(
Tables
4.5­
1
through
4.5­
5)
Absorbent
polymers,
organic
Acids,
solid,
organic
Asphalt
Bakelite
®
b
Cellulose
(
e.
g.,
Benelex
®
,
cotton
Conwed
®
,
paper,
rags,
rayon,
wood)
Cellulose
acetate
butyrate
Cellulose
propionate
Chlorinated
polyether
Detergent,
solid
(
e.
g.,
emulsifiers,
surfactants)
Fiberglass,
organic
Filter
media,
organic
Greases,
commercial
brands
Insulation,
organic
Leaded
rubber
(
e.
g.,
gloves,
aprons,
sheet
material)
Leather
Oil
(
e.
g.,
petroleum,
mineral)
Organophosphates
(
e.
g.,
tributyl
phosphate,
dibutyl
phosphate,
monobutyl
phosphite)
Paint,
dry
(
e.
g.,
floor/
wall
paint,
ALARA)
Plastics
[
e.
g.,
polycarbonate,
polyethylene,
polymethyl
methacrylate
(
Plexiglas
®
,
Lucite
®
)
,
polysulfone,
polytetrafluoroethylene
(
Teflon
®
)
,
polyvinyl
acetate,
polyvinyl
chloride,
polyvinylidene
chloride
(
saran)]
Polyamides
(
nylon)
Polychlorotrifluoroethylene
(
e.
g.,
Kel­
F
®
)
Polyesters
(
e.
g.,
Dacron
®
,
Mylar
®
)
Polyethylene
glycol
(
e.
g.,
Carbowax
®
)
Polyimides
Polyphenyl
methacrylate
Polypropylene
(
e.
g.,
Ful­
Flo
®
filters)
Polyurethane
Polyvinyl
alcohol
Resins
(
e.
g.,
aniline­
formaldehyde,
melamine­
formaldehyde,
organic
resins,
phenol­
formaldehyde,
phenolic
resins,
urea­
formaldehyde)
Rubber,
natural
or
synthetic
[
e.
g.,
chlorosulfonated
polyethylene
(
Hypalon
®
)
,
ethylene­
propylene
rubber,
EPDM,
polybutadiene,
polychloroprene
(
neoprene),
polyisobutylene,
polyisoprene,
polystyrene,
rubber
hydrochloride
(
pliofilm
®
)
]
Sand/
Soil
Waxes,
commercial
brands
aOther
chemicals
or
materials
not
identified
in
this
table
are
allowed
provided
that
they
meet
the
requirements
of
Section
4.5.3.
All
materials
in
the
final
waste
form
must
be
inert
(
nonreactive),
be
in
a
nonreactive
form,
or
have
been
rendered
nonreactive.
bBakelite
is
a
trademark
for
materials
that
can
be
composed
of
several
different
polymers,
including
polyethylene,
polypropylene,
epoxy,
phenolic,
polystyrene,
phenoxy,
perylene,
polysulfone,
ethylene
copolymers,
ABS,
acrylics,
and
vinyl
resins
and
compounds.
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HANFORD
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TRANSURANIC
WASTE
CERTIFICATION
PLAN
Table
4.5­
7
Allowable
Materials
for
Waste
Material
Types
III.
2
and
III.
3a
Homogeneous
Mixed
Organic
(
10%
by
weight)
and
Inorganic
(
90%
by
weight)
Materials
Any
material
in
Waste
Material
Types
I.
1,
I.
2,
I.
3,
II.
1,
II.
2,
II.
3,
or
III.
1
(
Tables
4.5­
1
through
4.5­
6),
provided
that
the
total
amount
of
solid
organic
material
and/
or
absorbed
or
adsorbed
water
is
less
than
or
equal
to
10
weight
percent
of
the
total
waste.
aOther
chemicals
or
materials
not
identified
in
this
table
are
allowed
provided
that
they
meet
the
requirements
of
Section
4.5.3.
All
materials
in
the
final
waste
form
must
be
inert
(
nonreactive),
be
in
a
nonreactive
form,
or
have
been
rendered
nonreactive.

Table
4.5­
8
Allowable
Materials
for
Waste
Material
Type
IV.
1a
Solidified
Organics
Any
material
in
Waste
Types
I,
II,
or
III
(
Tables
4.5­
1
through
4.5­
7)
Acids,
organic
Alcohols
(
e.
g.,
butanol,
ethanol,
isopropanol,
methanol)
Esters
(
e.
g.,
ethyl
acetate,
polyethylene
glycol
ester)
Ethers
(
e.
g.,
ethyl
ether)
Halogenated
organics
(
e.
g.,
bromoform;
carbon
tetrachloride;
chlorobenzene;
chloroform;
1,1­
dichloroethane;
1,2­
dichloroethane;
1,1­
dichloroethylene;
cis­
1,2­
dichloroethylene;
methylene
chloride;
1,1,2,2­
tetrachloroethane;
tetrachloroethylene;
1,1,1­
trichloroethane;
1,1,2­
trichloroethane;
trichloroethylene;
1,1,2­
trichloro­
1,2,2­
trifluoroethane)
Hydrocarbons,
aliphatic
(
e.
g.,
cyclohexane,
n­
paraffin
hydrocarbons)
Hydrocarbons,
aromatic
(
e.
g.,
benzene;
ethyl
benzene;
toluene;
1,2,4­
trimethylbenzene;
1,3,5­
trimethylbenzene;
xylene)
Ketones
(
e.
g.,
acetone,
methyl
ethyl
ketone,
methyl
isobutyl
ketone)
Trioctyl
phosphine
oxide
aOther
chemicals
or
materials
not
identified
in
this
table
are
allowed
provided
that
they
meet
the
requirements
of
Section
4.5.3.
All
materials
in
the
final
waste
form
must
be
inert
(
nonreactive),
be
in
a
nonreactive
form,
or
have
been
rendered
nonreactive.
HNF­
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HANFORD
SITE
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WASTE
CERTIFICATION
PLAN
4.6
GAS
GENERATION
REQUIREMENTS
4.6.1
Payload
Shipping
Category
4.6.1.1
Requirements
Gas
generation,
concentrations,
and
pressures
during
transport
of
CH
TRU
wastes
in
a
TRUPACT­
II
payloads
are
restricted
as
follows:

 
For
any
package
containing
water
and/
or
organic
substances
that
could
radiolytically
generate
combustible
gases,
determination
must
be
made
by
tests
and
measurements
or
by
analysis
of
a
representative
package
such
that
the
following
criterion
is
met
over
a
period
of
time
that
is
twice
the
expected
shipment
time
(
defined
in
Appendices
3.4,
3.5,
and
3.6
of
the
CH­
TRU
Payload
Appendices).
The
hydrogen
generated
must
be
limited
to
no
more
than
5
percent
by
volume
of
the
innermost
layer
of
confinement
(
or
equivalent
limits
for
other
inflammable
gases)
if
present
at
standard
temperature
and
pressure
(
STP).
 
The
gases
generated
in
the
payload
and
released
into
the
ICV
cavity
shall
be
controlled
to
maintain
the
pressure
within
the
TRUPACT­
II
ICV
cavity
below
the
acceptable
design
pressure
of
50
pounds­
per­
square­
inch
gauge
(
psig).

CH
TRU
waste
is
classified
into
payload
shipping
categories
to
evaluate
and
ensure
compliance
with
the
gas­
generation
requirements.
The
thermal
wattage
(
decay
heat)
allowed
in
each
payload
shipping
category
is
restricted
such
that
the
hydrogen
generated
during
twice
the
expected
shipment
time
results
in
a
molar
quantity
of
not
more
than
5
volume
percent
in
any
layer
of
confinement
in
the
payload
container
or
packaging.
A
shipping
category
is
defined
by
the
following
parameters:

 
Chemical
composition
of
the
waste
(
waste
type).
 
Gas­
generation
potential
of
the
waste
material
type
(
quantified
by
the
G
value
for
hydrogen)
which
is
the
number
of
molecules
of
hydrogen
generated
per
100
electron
volts
(
eV)
of
energy
absorbed).
Table
4.6­
2
of
this
Certification
Plan
lists
the
G
values
associated
with
the
various
waste
material
types
for
CH­
TRU
waste.
 
Gas
release
resistance
(
type
of
payload
container
and
type
and
maximum
number
of
confinement
layers
used).

For
any
given
payload
container,
the
shipping
category
provides
a
basis
to
determine
the
gasgeneration
potential
of
the
contents
and
the
resistance
to
gas
release
of
the
packaging
configuration.
This
enables
evaluation
of
compliance
with
the
gas­
generation
requirements
(
5
percent
limit
on
hydrogen
concentration).
Two
payload
shipping
category
notations
are
available.
A
shipping
site
may
use
either
notation.
Descriptions
of
the
two
notations
are
presented
below.
HNF­
2600,
REV
15
Page
100
of
281
5/
11/
2005
HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
Numeric
Shipping
Category
Notation
The
numeric
shipping
category
notation
(
initiated
in
the
CH­
TRAMPAC)
is
a
ten­
digit
code,
in
the
form
XX
YYYY
ZZZZ,
where
XX
=
the
waste
type,
which
indicates
the
chemical
composition
of
the
waste
YYYY
=
the
G­
value,
or
gas
generation
potential,
of
the
waste
material
type
multiplied
by
102
ZZZZ
=
the
resistance
to
hydrogen
release
of
the
packaging
configuration
multiplied
by
10­
4
A
description
of
the
parameters
follows.

Waste
Type
Payloads
for
the
TRUPACT­
II
package
are
subdivided
into
four
waste
types
based
on
physical
and
chemical
form
as
shown
in
Table
4.6­
1
of
this
section.
Table
4.6­
1
also
shows
the
shipping
category
notation
denoting
each
waste
type.

Waste
Material
Type
The
four
waste
types
can
be
further
subdivided
into
waste
material
types.
The
waste
material
types
define
the
gas
generation
potential
of
the
waste.
A
listing
of
the
chemicals/
materials
allowed
in
each
waste
material
type
is
presented
in
the
CH­
TRAMPAC,
Tables
4.6­
1
through
4.6­
4.
An
effective
G
value
quantifying
the
gas
generation
potential
of
each
waste
material
type
is
assigned
based
on
the
chemicals
allowed.
Table
4.6­
2
(
of
this
certification
plan
and
consistent
with
Section
5.0
of
the
CH­
TRAMPAC)
lists
the
waste
material
types
and
their
respective
bounding
G
values,
along
with
the
shipping
category
denoting
the
bounding
G
value.

Total
Resistance
The
determination
of
the
total
resistance
to
gas
release
of
a
payload
container
requires
knowledge
of
the
type
and
maximum
number
of
layers
of
confinement
used
to
package
waste.
Allowable
closure
methods
for
confinement
layers
are
specified
in
Appendix
3.8
of
the
CH­
TRU
Payload
Appendices.
The
plastic
layers
of
confinement
in
payload
containers
are
of
three
types
 
liner
bags,
inner
bags,
and
filtered
bags,
as
described
in
Section
2.9
of
the
CH­
TRAMPAC.
The
release
rates
for
these
types
of
bags
have
been
quantified.
Any
other
confinement
layers
used
shall
be
shown
to
be
equivalent
to
one
of
the
three
listed
above.

The
shipping
category
notation
used
to
denote
the
total
resistance
to
hydrogen
release
of
the
packaging
configuration
of
a
payload
container
is
the
sum
of
all
the
resistances
from
all
confinement
layers
(
seconds/
mole)
multiplied
by
10­
4,
rounded
up,
and
reported
as
digits
(
ZZZZ).
For
example,
the
shipping
category
notation
for
a
total
resistance
of
1,395,163
seconds/
mole
is
"
0140."
HNF­
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101
of
281
5/
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2005
HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
The
shipping
category
assignment
for
a
55­
gallon
drum
containing
solid
inorganic
waste
packaged
within
two
filtered,
plastic­
liner­
bag
layers
is:

20
0170
0140
where,

20
=
Waste
Type
II
0170
=
G
value
(
x
102)
of
Waste
Material
Type
II.
1
0140
=
Total
resistance
to
hydrogen
release
(
x
10­
4)
of
the
two
filtered
bags.

Alphanumeric
Shipping
Category
Notation
This
shipping
category
notation
(
used
through
Rev.
16
of
the
TRAMPAC)
was
based
on
the
same
parameters
as
the
numeric
notation
(
initiated
in
revision
17),
but
conveyed
the
information
through
a
different
set
of
parameters.

The
alpha­
numeric
shipping
category
notation
was
based
on
the
waste
material
type,
the
payload
containment
type,
and
the
type
and
number
of
confinement
layers
a
payload
contains.

Table
4.6­
1
Summary
of
Payload
Waste
Types
Waste
Typea
Waste
Typeb
Description
of
Examples
I
10
Solidified
Aqueous
or
Homogeneous
Inorganic
Solids
(<
1%
organics
 
not
including
packaging)
absorbed,
adsorbed
or
solidified
inorganic
liquid
soils,
concreted
inorganic
particulate
waste,
solidified
particulates,
or
sludges
formed
from
precipitates
II
20
Solid
Inorganics
Glass,
metals,
crucibles
Other
solid
inorganics
III
30
Solid
Organics
Plastics
(
e.
g.,
polyethylene,
polyvinyl
chloride)
Cellulose
(
e.
g.,
paper,
cloth,
wood)
Cemented
organic
solids
Other
solid
organics
IV
40
Solidified
Organics
Cemented
or
immobilized
organic
liquids
and
solids
aPayload
shipping
category
notation
used
through
TRUPACT­
II
SAR,
Rev.
16
bPayload
shipping
category
notation
used
through
TRUPACT­
II
SAR,
Rev.
17
Source:
Appendix
2.1
of
the
CH­
TRU
Payload
Appendices
HNF­
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HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
Table
4.6­
2
CH
TRU
Waste
Material
Types
and
G
Values
Waste
Material
Type
Typical
Material
Descriptiona
G
Valueb
Numeric
Shipping
Category
Notation
(
G
Value
x
102
(
YYYY)
I.
1
Absorbed,
adsorbed,
or
solidified
inorganic
liquid
1.6
0160
I.
2
Soils,
solidified
particulates,
or
sludges
formed
from
precipitation
1.3
0130
I.
3
Concerted
inorganic
particulate
waste
0.4
0040
II.
1
Solid
inorganic
materials
in
plastic
bags
(
watt*
year
 
0.012)
1.7
0170
II.
1
Solid
inorganic
materials
in
plastic
bags
(
watt*
year
>
0.012)
0.32
0032
II.
2
Solid
inorganic
materials
in
metal
cans
0
0000
II.
3
Homogeneous
solid
inorganic
materials
with
unbound
absorbed
ambient
moisture
( 
6
percent
by
weight)
in
metal
cans
0.08
0008
III.
1
Solid
organic
materials
(
watt*
year
 
0.012)
3.4
0340
III.
1
Solid
organic
materials
(
watt*
year
>
0.012)
1.09
0109
III.
2
Homogeneous
mixed
organic
(
10
percent
by
weight)
and
inorganic
(
90
percent
by
weight)
materials
in
metal
cans
(
watt*
year
 
0.012)
0.34
0034
III.
2
Homogeneous
mixed
organic
(
10
percent
by
weight)
and
inorganic
(
90
percent
by
weight)
materials
in
metal
cans
(
watt*
year
>
0.012)
0.11
0011
III.
3
Homogeneous
mixed
organic
(
10
percent
by
weight)
and
inorganic
(
90
percent
by
weight)
materials
in
plastic
bags
(
watt*
year
 
0.012)
1.85
0185
III.
3
Homogeneous
mixed
organic
(
10
percent
by
weight)
and
inorganic
(
90
percent
by
weight)
materials
in
plastic
bags
(
watt*
year
>
0.012)
0.4
0040
IV.
1
Solidified
organics
Unknown
test
9999
aAppendix
3.3
of
the
CH­
TRU
Payload
Appendices
provides
a
complete
discussion
of
watt*
year
criteria.
bDose­
dependent
G
values
for
waste
meeting
the
watt*
year
criteria
(
watt*
year
>
0.012)
cannot
be
used
if
absorbed,
adsorbed,
or
solidified
aqueous
materials
are
present
in
the
waste
(
see
Appendix
3.3
of
the
CH­
TRU
Appendices).
Appendices
3.1
and
3.2
of
the
CH­
TRU
Payload
Appendices
provide
a
complete
discussion
of
G
value.
HNF­
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2005
HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
Table
4.6­
3
Alpha­
numeric
Shipping
Category
Notation
for
Payload
Container
Configurations
Notation
Description
A
55­
gal.
drums
with
materials
in
additional
layers
of
confinement
(
such
as
rigid
liners[
s],
bag[
s],
and
can[
s]
and
includes
55­
gal.
drums
overpacked
in
a
TDOP)
B
Overpack
of
four
55­
gal.
drums
in
an
SWB
(
SWB
overpack)
C
SWB
with
materials
in
additional
layers
of
confinement
(
such
as
bag[
s]
and
can[
s])
D
Overpack
of
one
experimental
bin
in
an
SWB
E
Overpack
of
one
pipe
component
in
a
55­
gal.
drum
(
pipe
overpack)
Source:
Appendix
2.1,
Table
2.1­
3
of
CH­
TRU
Payload
Appendices
Table
4.6­
4
Alpha­
numeric
Shipping
Category
Notation
for
Layers
of
Confinement
in
Payload
Containers
Notation
Description
0
No
closed
bags
around
waste
1
Up
to
a
maximum
of
1
closed
bag
around
waste
2
Up
to
a
maximum
of
2
closed
layers
of
bags
around
waste
3
Up
to
a
maximum
of
3
closed
layers
of
bags
around
waste
4
Up
to
a
maximum
of
4
closed
layers
of
bags
around
waste
5
Up
to
a
maximum
of
5
closed
layers
of
bags
around
waste
6
Up
to
a
maximum
of
6
closed
layers
of
bags
around
waste
M
Metal
container(
s)
as
the
innermost
layer
of
confinement
a
For
Waste
Types
II
and
III
packaged
in
drums,
denotes
a
minimum
of
2
liner
bags
b
For
all
waste
types
packaged
in
SWBs,
denotes
a
minimum
of
1
SWB
liner
bag
f
All
layers
of
bags
around
waste
are
vented
with
a
minimum
of
1
filter
vent
T
Payload
container
qualified
for
shipment
under
the
test
category.
Source:
Appendix
2.1,
Table
2.1­
4
of
CH­
TRU
Payload
Appendices
HNF­
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HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
The
shipping
category
assignment
for
a
55­
gallon
drum
with
alpha­
numeric
shipping
category
notation
is:

II.
1A2af
where,

II.
1
=
the
waste
material
type
(
solid
inorganic
materials
in
plastic
bags
[
table
4.6­
2
of
this
Certification
Plan])

A
=
the
type
of
payload
container
(
55­
gallon
drum
[
table
4.6­
3
of
this
Certification
Plan])

2
=
the
number
of
confinement
layers
(
2
bag
layers
[
table
4.6­
4
of
this
Certification
Plan])

af
=
the
type
of
confinement
layers
(
filtered
drum
liner
bags
[
table
4.6­
4
of
this
Certification
Plan]).

Each
payload
container
shall
be
assigned
to
a
payload
shipping
category
in
a
content
code
approved
by
the
WIPP
CH­
TRU
Payload
Engineer
that
shall
have
the
following
components:

 
Waste
type
 
Waste
material
type
that
defines
the
gas
generation
potential
 
Total
resistance
1.
Confinement
layer:
The
inner
layers
of
confinement
around
the
waste
materials
in
a
payload
container
shall
be
a
plastic
bag
and/
or
metal
cans
that
meet
the
specifications
outlined
in
Appendix
3.8
of
the
CH­
TRU
Payload
Appendices.
Any
other
confinement
layers
must
be
equivalent
by
demonstration
of
hydrogen
release
rates
equal
to
or
greater
than
those
established
in
Appendix
3.8
of
the
CH_
TRU
Payload
Appendices.

2.
Rigid
Liner:
The
rigid
liner
and
lid,
if
present,
in
a
payload
container
shall
contain
a
 
0.3­
in.
minimum
diameter
hole,
or
a
filter
with
a
hydrogen
release
rate
equivalent
to
or
greater
than
a
0.3­
in.
minimum
diameter
hole.
Otherwise,
the
liner
must
be
treated
as
any
other
confinement
layer
with
the
associated
resistance
of
the
liner
hole
diameter
or
filter
calculated
in
accordance
with
Appendix
2.2
of
the
CH­
TRU
Payload
Appendices.

3.
Shipping
Period:
The
conditions
specified
in
Appendix
3.6
of
the
CH­
TRU
Payload
Appendices
must
be
met
for
use
of
the
Controlled
Shipment
shipping
period
(
10
days).
For
other
shipments
(
not
Controlled
Shipments),
the
appropriate
shipping
period
[
60
days
(
Appendix
3.4
of
the
CH­
TRU
Payload
Appendices)
or
20
days
(
Appendix
3.5
of
the
CH­
TRU
Payload
Appendices)]
shall
be
applied
based
on
the
transport
distance.
HNF­
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HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
4.6.1.2
Compliance
and
Verification
For
retrievably
stored
waste,
AK
is
verified
by
radiography
and/
or
VE.
Before
the
completion
of
waste
certification
and
transport,
the
assigned
shipping
category
must
contain
an
approved
content
code.

Wastes
generated
at
the
Hanford
site
will
be
categorized
into
several
waste
streams.
The
CH­
TRUCON
document
generally
lists
Hanford
site
waste
streams
and
their
associated
waste
material
types
and
transportation
parameters
(
e.
g.,
shipping
categories,
decay
heat,
total
resistance,
confinement
layers).

Numeric
or
Alpha­
Numeric
Shipping
Categories
The
TCO
and
WCO
shall
verify
compliance
by
looking
up
the
numeric
shipping
category
for
the
appropriate
content
code
in
the
CH­
TRUCON
document,
comparing
the
approved
content
code
assigned
shipping
categories,
consistent
with
WMP­
400,
Sections
2.1.5
and
7.1.8
respectively.
If
a
content
code
is
not
approved,
a
request
must
be
submitted
to
the
WIPP
CH­
TRU
Payload
Engineer
for
approval.

Hanford
does
not
have
alpha­
numeric
shipping
categories.
Total
Resistance
Confinement
layers
shall
be
determined
and
verified
through
AK,
RTR,
VE,
and/
or
VE
technique
consistent
with
WMP­
400,
Sections
7.1.9,
7.1.3,
7.1.8,
and
7.1.10,
respectively.
If
any
other
type
of
confinement
and
layer
other
than
those
noted
in
table
4­
4
of
this
Certification
Plan
are
used,
equivalency
shall
be
established
by
demonstration
of
hydrogen
release
rate
greater
than
or
equal
to
the
approved
confinement
layers.

The
WCO
verifies
and
documents
confinement
layers
consistent
with
WMP­
400,
Sections
7.1.5
and
7.1.8.

Rigid
liners
shall
be
vented
as
described
in
Section2.5
of
the
CH­
TRAMPAC
or
Section
2.9
of
the
CH­
TRAMPAC.
The
WCO
verifies
and
documents
the
compliance
consistent
with
WMP­
400,
Sections
7.1.5
and
7.1.8.

Decay
Heat
The
TCO
and
WCO
verify
and
document
the
maximum
allowable
decay
heat
plus
the
measurement
error
(
one
standard
deviation)
in
accordance
with
WMP­
400,
Sections
2.1.5,
and
7.1.8
respectively
and
7.1.5.

Refer
to
Appendix
A
column
"
CH­
TRAMPAC
(
and
certification
Plan
Section,
if
applicable)
row
5.0,
which
contains
the
titles
of
applicable
procedures
that
implement
the
requirements
of
this
subsection.
HNF­
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HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
4.6.2
Flammable
(
Gas/
VOC)
Concentration
Limits
4.6.2.1
Requirements
As
discussed
in
Appendices
6.1,
6.5,
and
6.6
of
the
CH­
TRU
Payload
Appendices,
the
primary
mechanism
for
potential
flammable
gas
generation
in
TRU
wastes
is
radiolysis.
TRU
wastes
to
be
transported
in
the
TRUPACT­
II
are
restricted
so
that
no
flammable
mixtures
can
occur
in
any
layer
of
confinement
during
shipment.
While
the
predominant
flammable
gas
of
concern
is
hydrogen,
the
presence
of
methane
and
flammable
volatile
organic
compounds
(
VOCs)
is
also
limited
along
with
hydrogen
to
ensure
the
absence
of
flammable
(
gas/
VOC)
mixtures
in
TRU
waste
payloads.

4.6.2.2
Compliance
and
Verification
The
evaluation
of
compliance
with
flammable
(
gas/
VOC)
limits
occurs
under
either
the
analytical
category
or
the
test
category.

Compliance
with
the
flammable
(
gas/
VOC)
limits
can
be
demonstrated
under
the
analytical
category
if
the
payload
container
meets
both
of
the
following:

 
The
total
concentration
of
potentially
flammable
VOCs
within
the
payload
container
headspace
is
less
than
or
equal
to
500
parts
per
million
(
ppm)
 
The
payload
container
is
classified
as
Waste
Types
I
(
10),
II
(
20),
or
III
(
30).

If
the
payload
container
headspace
exceeds
500
ppm
flammable
VOCs
or
is
classified
as
Waste
Type
IV
(
Hanford
will
not
be
shipping
Waste
Type
IV),
compliance
with
the
flammable
(
gas/
VOC)
concentration
limits
must
be
demonstrated
under
the
test
category.

If
the
payload
container
is
proposed
for
shipment
in
a
payload
assembly
comprised
of
payload
containers
of
the
same
shipping
category,
compliance
with
the
analytical
decay
heat
limit
specified
per
container
based
on
the
payload
shipping
category
is
required.
If
the
payload
container
meets
the
analytical
decay
heat
limit,
compliance
with
the
flammable
(
gas/
VOC)
limits
is
ensured.
The
analytical
decay
heat
limit
for
each
shipping
category
is
described
in
Section
4.6.2.3.

If
the
payload
container
exceeds
the
analytical
decay
heat
limit,
compliance
with
the
flammable
(
gas/
VOC)
limits
may
be
demonstrated
through
mixing
in
a
payload
assembly
of
different
shipping
categories
as
described
in
Section
4.7.4.
Alternatively,
compliance
with
the
flammable
(
gas/
VOC)
limits
may
be
demonstrated
under
the
test
category,
as
described
below.
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Compliance
with
the
flammable
(
gas/
VOC)
limits
is
demonstrated
under
the
test
category
if
the
payload
container
falls
into
one
or
more
of
the
following:

 
The
total
concentration
of
potentially
flammable
VOCs
within
the
payload
container
headspace
exceeds
500
ppm.
Waste
Types
I
(
10),
II
(
20),
and
III
(
30)
belong
in
this
category.
 
The
total
concentration
of
potentially
flammable
VOCs
within
the
payload
container
headspace
is
less
than
or
equal
to
500
ppm,
but
the
decay
heat
loading
of
the
payload
container
exceeds
the
analytical
limit
for
the
shipping
category
of
the
payload
container.
Waste
Types
I
(
10),
II
(
20),
and
III
(
30)
belong
in
this
category.
 
A
waste
form
does
not
have
a
fully
characterized
bounding
G
value
from
previous
sampling
or
waste
stream
analysis.
Waste
Type
IV
(
40)
belongs
in
this
category.

For
test
category
payload
containers
of
Waste
Types
I
(
10),
II
(
20),
and
III
(
30),
the
compliance
evaluation
for
flammable
(
gas/
VOC)
limits
may
be
based
on
measurement
of
the
headspace
gas,
as
described
in
Section
4.6.2.4
under
Assignment
of
DACs
for
Common
Packaging
Configurations.

The
implementation
of
compliance
methods
summarized
above
for
flammable
(
gas/
VOC)
limits
is
illustrated
in
Figures
4.6­
1
through
4.6­
5
and
detailed
in
Steps
1
through
5
below.
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Figure
4.6­
1
 
Logic
Diagram
for
Compliance
with
Flammable
(
Gas/
VOC)
Limits
by
Analysis
Payload
Container
Data
Package
Waste
Types
I,
II,
or
III
Waste
Type
IV
Yes
Yes
No
No
No
Figure
4.6­
2
Drum
Age
Criteria
Section
4.6.2.4
Section
4.6.2.5
Section
4.7.4
Figure
4.6­
4
Testing
Figure
4.6­
3
Measurement
Figure
4.6­
5
MixCat
Payload
Container
Meets
Flammable
(
Gas/
VOC)
Limits
Analytical
Category
Section
4.6.2.5
Flammable
VOCs
 
500
ppm
based
on
container
data
package
All
Payload
Containers
Same
Shipping
Category
Decay
Heat
 
Analytical
Limit
Start
Yes
1a
1b
Waste
Type
1d
1f
1h
1c
1e
1g
1i
1j
Section
4.6.2.3
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Figure
4.6­
2
 
Logic
Diagram
for
Drum
Age
Criteria
for
Flammable
VOC
Measurement
From
Figure
4.6­
1,
Step
Determine
Steady­
State
Headspace
Flammable
VOC
Concentration
Apply
Prediction
Factors
to
Determine
Flammable
VOC
Concentration
in
Inner
Confinement
Layer
and
Update
Payload
Container
Data
Package
Payload
Container
Meets
Drum
Age
Criteria
for
Flammable
VOC
Measurement
Section4.6.2.4
Section
4.6.2.4
Section
4.6.2.4
No
No
Yes
Yes
Flammable
VOCs
 
500
ppm
based
on
measurement
1c
2a
2c
2b
2d
Update
Payload
Container
Data
Package
2f
To
Figure
4.6­
3
Measurement
2e
To
Figure
4.6­
1
"
Start"
2g
Section
4.6.2.5
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Figure
4.6­
3
 
Logic
Diagram
for
Compliance
with
Flammable
(
Gas/
VOC)
Limits
by
Measurement
Yes
Yes
No
No
No
To
Figure
4.6­
5
MixCat
Mitigate
and
Update
Payload
Container
Data
Package
Payload
Container
Meets
Flammable
(
Gas/
VOC)
Limits
Test
Category
(
Measurement)
All
Payload
Containers
Same
Shipping
Category
From
Figure
4.6­
1,
Step
or
Figure
4.6­
2,
Step
Yes
3a
1i
2e
3d
Flammable
(
Gas/
VOC)
Concentration
 
Limit
3f
3e
To
Figure
4.6­
1
"
Start"
3c
To
Figure
4.6­
4
Testing
3g
3b
3h
CH4
 
1,250
ppm
Section
4.7.4
Section
4.6.2.5
and
Appendix
3.10*
Section
4.6.2.5
*
Note:
Referenced
Appendix
located
in
the
CH­
TRU
Payload
Appendices
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Figure
4.6­
4
 
Logic
Diagram
for
Compliance
with
Flammable
(
Gas/
VOC)
Limits
by
Testing
Yes
Yes
Yes
No
No
To
Figure
4.6­
5
MixCat
Section
4.7.4
Mitigate
and
Update
Payload
Container
Data
Package
Payload
Container
Meets
Flammable
(
Gas/
VOC)
Limits
Test
Category
(
Testing)
All
Payload
Containers
Same
Shipping
Category
From
Figure
4.6­
1,
Step
or
Figure
4.6­
3,
Step
CH
4
 
1,250
ppm
Yes
No
3g
1e
4a
4d
4f
4e
To
Figure
4.6­
1
"
Start"
4c
To
Figure
4.6­
1
"
Start"
4h
4i
4g
Mitigate
and
Update
Payload
Container
Data
Package
4b
Section
4.6.2.5
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Figure
4.6­
5
 
Logic
Diagram
for
Compliance
with
Flammable
(
Gas/
VOC)
Limits
by
Mixing
of
Shipping
Categories
in
a
Payload
Assembly
To
Step
5a
Above
Flammability
Index
for
Each
Container
in
Assembly
 
50,000
No
No
Data
Packages
for
Containers
in
Proposed
Payload
Assembly
Mitigate
and
Update
Payload
Container
Data
Package
Compile
Data
Packages
for
Revised
Payload
Assembly
From
Figure
4.6­
1,
Step
or
Figure
4.6­
3,
Step
or
Figure
4.6­
4,
Step
Payload
Container
Meets
Flammable
(
Gas/
VOC)
Limits
(
MixCat)
Yes
Yes
5h
5f
5d
5b
Reconfigure
Payload
Assembly
5c
5a
1g
3e
4e
To
Figure
4.6­
1
"
Start"
5e
*
Note:
Referenced
Appendix
located
in
the
CH­
TRU
Payload
Appendices
5g
5a
Section
4.7.4
and
Appendix
2.4*
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4.6.2.2.1
Analytical
Category:
Compliance
with
Flammable
(
Gas/
VOC)
Limits
Figure
4.6­
1
presents
the
logic
for
performing
the
compliance
evaluation
for
flammable
(
gas/
VOC)
limits
by
analysis,
which
consists
of
the
following
steps:

Step
1a
,
Payload
Container
Data
Package
 
The
starting
point
for
compliance
evaluation
by
analysis
is
the
payload
container
data
package,
which
includes
all
data
associated
with
the
payload
container.
These
data
are
gathered
from
one
or
more
of
the
methods
of
payload
compliance
listed
and
defined
in
Section
4.0
(
i.
e.,
visual
examination,
visual
inspection,
radiography,
records
and
database
information,
administrative
and
procurement
controls,
sampling
programs,
and
measurement).

Step
1b
,
Flammable
VOCs
 
500
ppm
 
Can
it
be
established
that
the
concentration
of
flammable
VOCs
present
in
the
headspace
of
the
payload
container
is
 
500
ppm?
The
concentration
of
flammable
VOCs
present
in
the
headspace
of
the
payload
container
is
determined
based
on
the
information
contained
in
the
payload
container
data
package.
Data
used
to
make
this
determination
consist
of
process
knowledge
(
e.
g.,
knowledge
of
waste
generation
processes
and
chemical
and
material
inputs
to
the
process)
and
may
include
results
from
a
headspace
gas
sampling
program.
A
list
of
flammable
VOCs
is
presented
in
Section
4.6.2.4.
If
a
concentration
of
flammable
VOCs
in
the
payload
container
headspace
of
less
than
or
equal
to
500
ppm
cannot
be
established
based
on
the
payload
container
data
package,
the
compliance
evaluation
shall
proceed
to
Step
1c
,
Drum
Age
Criteria.
If
it
can
be
determined
based
on
available
data
that
no
flammable
VOCs
are
present
in
the
payload
container,
or
if
it
can
be
established
that
the
total
flammable
VOC
concentration
in
the
payload
container
headspace
is
less
than
or
equal
to
500
ppm,
the
compliance
evaluation
shall
proceed
to
Step
1d
,
Waste
Type.

Note:
For
compliance
with
the
analytical
category
limit
on
VOC
concentration,
VOC
absorbing
or
adsorbing
material
(
such
as
granular
activated
carbon
to
adsorb
carbon
tetrachloride)
may
be
placed
in
a
payload
container
provided
that
site
personnel
can
verify
or
demonstrate
the
following
through
testing,
analysis,
or
knowledge
of
the
process:

The
absorbent/
adsorbent
remains
effective
in
retaining
VOCs
from
the
time
of
waste
packaging
through
the
end
of
the
maximum
shipping
period
in
the
TRUPACT­
II,

A
flammable
mixture
of
gases
does
not
exist
in
the
innermost
layer
of
confinement,
and
The
total
concentration
of
potentially
flammable
VOCs
does
not
exceed
500
ppm
in
the
headspace
of
a
payload
container.

Step
1c
,
Drum
Age
Criteria
 
If
a
payload
container
headspace
concentration
of
flammable
VOCs
 
500
ppm
cannot
be
established
based
on
the
payload
container
data
package,
the
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flammable
VOC
concentration
of
the
payload
container
headspace
must
be
measured
in
accordance
with
the
logic
presented
in
Figure
4.6­
2
and
Section
4.6.2.2.2,
Drum
Age
Criteria
for
Flammable
VOC
Measurement.

Step
1d
,
Waste
Type
 
What
is
the
waste
type
assigned
to
the
payload
container?
If
the
payload
container
under
evaluation
is
classified
as
Waste
Type
IV
(
unknown
G
value),
it
belongs
in
the
"
Test
Category,"
and
the
compliance
evaluation
for
flammable
(
gas/
VOC)
limits
shall
proceed
to
Step
1e
,
Testing.
If
the
payload
container
under
evaluation
is
classified
as
Waste
Type
I,
II,
or
III,
the
evaluation
shall
proceed
to
Step
1f
,
All
Payload
Containers
Same
Shipping
Category.

Step
1e
,
Testing
 
If
the
payload
container
under
evaluation
is
classified
as
Waste
Type
IV,
the
compliance
with
flammable
(
gas/
VOC)
limits
must
be
evaluated
through
testing
performed
in
accordance
with
the
logic
presented
in
Figure
4.6­
4
and
Section
4.6.2.2.4,
Test
Category:
Compliance
with
Flammable
(
Gas/
VOC)
Limits
by
Testing.

Step
1f
,
All
Payload
Containers
Same
Shipping
Category
 
Does
the
payload
container
proposed
belong
to
the
same
shipping
category
as
the
other
containers
proposed
for
payload
assembly?
If
the
payload
container
is
proposed
for
shipment
in
a
payload
assembly
comprised
of
containers
of
different
shipping
categories
and/
or
dunnage
containers,
the
compliance
evaluation
shall
proceed
to
Step
1g
,
MixCat.
If
the
payload
container
is
proposed
for
shipment
in
a
payload
assembly
comprised
of
payload
containers
of
the
same
shipping
category,
the
evaluation
shall
proceed
to
Step
1h
,
Decay
Heat
 
Analytical
Limit.

Step
1g
,
MixCat
 
If
the
payload
container
is
proposed
for
shipment
with
containers
of
different
shipping
categories
and/
or
dunnage
containers,
the
compliance
evaluation
shall
proceed
as
presented
in
Figure
4.6­
5
and
Section
4.6.2.2.5,
Compliance
with
Flammable
(
Gas/
VOC)
Limits
by
Mixing
of
Shipping
Categories
in
a
Payload
Assembly.

Step
1h
,
Decay
Heat
 
Analytical
Limit
 
Does
the
payload
container
exceed
the
analytical
decay
heat
limit?
For
applicable
payload
containers
(
i.
e.,
Waste
Types
I,
II,
or
III
with
flammable
VOCs
less
than
or
equal
to
500
ppm
in
the
headspace
and
proposed
for
shipment
with
containers
belonging
to
the
same
shipping
category),
compliance
with
the
analytical
decay
heat
limit
may
be
evaluated.
The
derivation
of
decay
heat
limits
for
shipping
categories
is
presented
in
Section
4.6.2.3.
If
the
payload
container
exceeds
the
analytical
decay
heat
limit,
the
compliance
evaluation
shall
proceed
to
Step
1i
,
Measurement.
If
the
payload
container
meets
the
decay
heat
limit,
the
flammable
(
gas/
VOC)
limits
are
met
and
the
compliance
evaluation
is
complete
(
see
Step
1j
,
Payload
Container
Meets
Flammable
(
Gas/
VOC)
Limits.

Step
1i
,
Measurement
 
If
a
payload
container
exceeds
the
analytical
decay
heat
limit,
compliance
with
the
flammable
(
gas/
VOC)
limits
must
be
evaluated
through
headspace
gas
measurement
performed
in
accordance
with
the
logic
presented
in
Figure
4.6­
3
and
Section
4.6.2.2.3,
Test
Category:
Compliance
with
Flammable
(
Gas/
VOC)
Limits
by
Measurement.
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Step
1j
,
Payload
Container
Meets
Flammable
(
Gas/
VOC)
Limits
 
All
payload
containers
reaching
this
step
meet
the
flammable
(
gas/
VOC)
limits
and
are
eligible
for
shipment
if
all
other
transportation
requirements
are
satisfied.

4.6.2.2.2
Drum
Age
Criteria
for
Flammable
VOC
Measurement
If
a
payload
container
headspace
concentration
of
flammable
VOCs
 
500
ppm
cannot
be
established
based
on
the
payload
container
data
package
(
as
determined
in
Step
1b
of
Figure
4.6­
1),
the
flammable
VOC
concentration
of
the
payload
container
headspace
must
be
measured.
Figure
4.6­
2
presents
the
logic
for
the
compliance
evaluation
for
drum
age
criteria
(
DAC)
and
flammable
VOC
measurement,
which
consists
of
the
following
steps:

Step
2a
,
Payload
Container
Meets
Drum
Age
Criteria
for
Flammable
VOC
Measurement
­
Does
the
payload
container
meet
the
DAC
for
measurement
of
headspace
flammable
VOCs?
The
methodology
and
logic
for
determining
DAC
values
for
payload
containers
is
specified
in
Appendix
3.9
of
the
CH­
TRU
Payload
Appendices
and
Section
4.6.2.4.
If
the
payload
container
has
not
yet
met
the
DAC
specified
for
the
applicable
packaging
configuration,
the
evaluation
shall
proceed
to
Step
2b
,
Determine
Steady­
State
Headspace
Flammable
VOC
Concentration.
If
the
payload
container
meets
the
applicable
DAC,
the
evaluation
shall
proceed
to
Step
2c
,
Flammable
VOCs
 
500
ppm.

Step
2b
,
Determine
Steady­
State
Headspace
Flammable
VOC
Concentration
 
If
the
payload
container
has
not
yet
met
the
DAC
specified
for
the
applicable
packaging
configuration,
the
90­
percent
steady­
state
headspace
flammable
VOC
concentration
must
be
determined
from
the
measured
concentration
as
described
in
Appendix
3.9
of
the
CH­
TRU
Payload
Appendices.
Following
the
determination
of
this
value,
the
evaluation
shall
proceed
to
Step
2c
,
Flammable
VOCs
 
500
ppm.

Step
2c
,
Flammable
VOCs
 
500
ppm
 
Is
the
headspace
flammable
VOC
concentration
less
than
or
equal
to
500
ppm?
If
the
measured
or
calculated
steady­
state
payload
container
headspace
flammable
VOC
concentration
is
less
than
or
equal
to
500
ppm
(
i.
e.,
VOC
contribution
to
flammability
is
expected
to
be
negligible),
the
evaluation
shall
proceed
to
Step
2f
,
Update
Payload
Container
Data
Package.
If
the
steady­
state
payload
container
headspace
flammable
VOC
concentration
exceeds
500
ppm,
the
evaluation
shall
proceed
to
Step
2d
,
Apply
Prediction
Factors
to
Determine
Flammable
VOC
Concentration
in
Inner
Confinement
Layer
and
Update
Payload
Container
Data
Package.

Step
2d
,
Apply
Prediction
Factors
to
Determine
Flammable
VOC
Concentration
in
Inner
Confinement
Layer
and
Update
Payload
Container
Data
Package
 
If
the
steady­
state
payload
container
headspace
flammable
VOC
concentration
exceeds
500
ppm,
the
payload
container
belongs
in
the
test
category.
Prediction
factors
shall
be
applied,
as
described
in
Appendix
3.9
of
the
CH­
TRU
Payload
Appendices,
to
determine
flammable
VOC
concentration
in
the
innermost
confinement
layer.
Following
the
application
of
the
prediction
factors,
the
payload
container
data
package
shall
be
updated
and
the
evaluation
shall
proceed
to
Step
2e
,
Measurement.
HNF­
2600,
REV
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HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
Step
2e
,
Measurement
 
If
a
payload
container
headspace
flammable
VOC
concentration
exceeds
500
ppm
and
the
prediction
factor
has
been
applied
to
determine
the
flammable
VOC
concentration
in
the
innermost
confinement
layer,
compliance
with
the
flammable
(
gas/
VOC)
limits
must
be
evaluated
through
headspace
gas
measurement
performed
in
accordance
with
the
logic
presented
in
Figure
4.6­
3
and
Section
4.6.2.2.3,
Test
Category:
Compliance
with
Flammable
(
Gas/
VOC)
Limits
by
Measurement.

Step
2f
,
Update
Payload
Container
Data
Package
 
If
the
measured
or
calculated
steady­
state
payload
container
headspace
flammable
VOC
concentration
is
less
than
or
equal
to
500
ppm,
the
data
package
for
the
payload
container
shall
be
updated,
and
the
compliance
evaluation
shall
proceed
to
Step
2g
,
"
Start."

Step
2g
,
"
Start"
 
Following
the
documentation
of
the
payload
container
headspace
flammable
VOC
concentration
of
less
than
or
equal
to
500
ppm,
the
compliance
evaluation
shall
start
again
as
described
in
Figure
4.6­
1
and
Section
4.6.2.2.1,
Analytical
Category:
Compliance
with
Flammable
(
Gas/
VOC)
Limits.

4.6.2.2.3
Test
Category:
Compliance
with
Flammable
(
Gas/
VOC)
Limits
by
Measurement
If
the
payload
container
under
evaluation
exceeds
the
analytical
decay
heat
limit
(
as
determined
in
Step
1h
of
Figure
4.6­
1)
or
if
the
concentration
of
flammable
VOCs
in
the
payload
container
headspace
exceeds
500
ppm
(
as
determined
in
Step
2c
of
Figure
4.6­
2),
the
container
belongs
in
the
test
category.
One
option
under
the
test
category
consists
of
evaluation
based
on
measurement
of
the
payload
container
headspace
flammable
(
gas/
VOC)
concentration.
Figure
4.6­
3
presents
the
logic
for
performing
the
compliance
evaluation
for
flammable
(
gas/
VOC)
limits
by
measurement,
which
consists
of
the
following
steps:

Step
3a
,
CH4
 
1,250
ppm
 
Is
the
payload
container
headspace
methane
concentration
less
than
or
equal
to
1,250
ppm?
The
concentration
of
methane
present
in
the
headspace
of
the
payload
container
must
be
measured
in
accordance
with
the
headspace
measurement
methods
discussed
in
Section
4.6.2.5.
If
the
payload
container
headspace
methane
concentration
exceeds
1,250
ppm,
the
payload
container
cannot
be
approved
for
shipment
in
its
current
condition.
Mitigation
measures
must
be
taken
under
Step
3b
,
Mitigate
and
Update
Payload
Container
Data
Package.
If
the
payload
container
headspace
methane
concentration
is
less
than
or
equal
to
1,250
ppm
(
ensuring
that
methane
contribution
to
flammability
is
negligible),
the
compliance
evaluation
shall
proceed
to
Step
3d
,
All
Payload
Containers
Same
Shipping
Category.

Step
3b
,
Mitigate
and
Update
Payload
Container
Data
Package
 
If
the
payload
container
headspace
methane
concentration
exceeds
1,250
ppm,
the
payload
container
is
not
eligible
for
shipment
and
must
be
segregated
for
repackaging,
treatment,
or
other
mitigation
measures.
Following
the
completion
of
mitigation
measures,
the
compliance
evaluation
shall
proceed
to
Step
3c
,
"
Start."
HNF­
2600,
REV
15
Page
117
of
281
5/
11/
2005
HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
Step
3c
,
"
Start"
 
Following
the
completion
and
documentation
of
mitigation
measures
to
ensure
that
the
payload
container
headspace
methane
concentration
is
less
than
or
equal
to
1,250
ppm,
the
compliance
evaluation
shall
start
again
as
described
in
Figure
4.6­
1
and
Section
4.6.2.2.1,
Analytical
Category:
Compliance
with
Flammable
(
Gas/
VOC)
Limits.

Step
3d
,
All
Payload
Containers
Same
Shipping
Category
 
Does
the
payload
container
proposed
belong
to
the
same
shipping
category
as
the
other
containers
proposed
for
payload
assembly?
If
the
payload
container
is
proposed
for
shipment
in
a
payload
assembly
comprised
of
containers
of
different
shipping
categories
and/
or
dunnage
containers,
the
compliance
evaluation
shall
proceed
to
Step
3e
,
MixCat.
If
the
payload
container
is
proposed
for
shipment
in
a
payload
assembly
comprised
of
payload
containers
of
the
same
shipping
category,
the
evaluation
shall
proceed
to
Step
3f
,
Flammable
(
Gas/
VOC)
Concentration
 
Limit.

Step
3e
,
MixCat
 
If
the
payload
container
is
proposed
for
shipment
with
containers
of
different
shipping
categories
and/
or
dunnage
containers,
the
compliance
evaluation
shall
proceed
as
presented
in
Figure
4.6­
5
and
Section
4.6.2.2.5,
Compliance
with
Flammable
(
Gas/
VOC)
Limits
by
Mixing
of
Shipping
Categories
in
a
Payload
Assembly.

Step
3f
,
Flammable
(
Gas/
VOC)
Concentration
 
Limit
 
Is
the
sum
of
the
flammable
(
gas/
VOC)
concentrations
less
than
or
equal
to
the
mixture
lower
explosive
limit
(
MLEL)?
If
the
payload
container
is
proposed
for
shipment
in
a
payload
assembly
comprised
of
payload
containers
of
the
same
shipping
category,
the
flammable
(
gas/
VOC)
concentration
within
the
innermost
layer
of
confinement
must
be
determined
using
the
measured
headspace
flammable
(
gas/
VOC)
concentrations
and
the
time
history
of
the
payload
container,
as
described
in
Section
4.6.2.5
and
Appendix
3.10
of
the
CH­
TRU
Payload
Appendices.
A
specific
MLEL
shall
be
calculated
for
the
payload
container,
as
described
in
Section
4.6.2.5.
If
the
sum
of
the
flammable
(
gas/
VOC)
concentrations
in
the
innermost
layer
of
confinement
exceeds
the
MLEL,
the
compliance
evaluation
shall
proceed
to
Step
3g
,
Testing.
If
the
sum
of
the
flammable
(
gas/
VOC)
concentrations
in
the
innermost
layer
of
confinement
is
less
than
or
equal
to
the
MLEL,
the
flammable
(
gas/
VOC)
limits
are
met
and
the
compliance
evaluation
is
complete
(
see
Step
3h
,
Payload
Container
Meets
Flammable
(
Gas/
VOC)
Limits).

Step
3g
,
Testing
 
If
the
sum
of
the
flammable
(
gas/
VOC)
concentration
in
the
innermost
layer
of
confinement
exceeds
the
MLEL,
the
compliance
with
flammable
(
gas/
VOC)
limits
must
be
evaluated
through
testing
performed
in
accordance
with
the
logic
presented
in
Figure
4.6­
4
and
Section
4.6.2.2.4,
Test
Category:
Compliance
with
Flammable
(
Gas/
VOC)
Limits
by
Testing.

Step
3h
,
Payload
Container
Meets
Flammable
(
Gas/
VOC)
Limits
 
All
payload
containers
reaching
this
step
meet
the
flammable
(
gas/
VOC)
limits
and
are
eligible
for
shipment
if
all
other
transportation
requirements
are
satisfied.

4.6.2.2.4
Test
Category:
Compliance
with
Flammable
(
Gas/
VOC)
Limits
by
Testing
If
the
payload
container
under
evaluation
belongs
to
Waste
Type
IV
(
as
determined
in
Step
1d
of
Figure
4.6­
1)
or
if
the
flammable
(
gas/
VOC)
concentrations
exceed
the
MLEL
(
as
determined
HNF­
2600,
REV
15
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2005
HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
in
Step
3f
of
Figure
4.6­
3),
the
container
belongs
in
the
test
category,
and
compliance
with
flammable
(
gas/
VOC)
limits
must
be
evaluated
by
testing.

Figure
4.6­
4
presents
the
logic
for
performing
the
compliance
evaluation
for
flammable
(
gas/
VOC)
limits
by
testing,
which
consists
of
the
following
steps:

Step
4a
,
CH4
 
1,250
ppm
 
Is
the
payload
container
headspace
methane
concentration
less
than
or
equal
to
1,250
ppm?
The
concentration
of
methane
present
in
the
headspace
of
the
payload
container
must
be
measured
in
accordance
with
the
headspace
measurement
methods
discussed
in
Section
4.6.2.5.
If
the
payload
container
headspace
methane
concentration
exceeds
1,250
ppm,
the
payload
container
cannot
be
approved
for
shipment
in
its
current
condition.
Mitigation
measures
must
be
taken
under
Step
4b
,
Mitigate
and
Update
Payload
Container
Data
Package.
If
the
payload
container
headspace
methane
concentration
is
less
than
or
equal
to
1,250
ppm
(
ensuring
that
methane
contribution
to
flammability
is
negligible),
the
compliance
evaluation
shall
proceed
to
Step
4d
,
All
Payload
Containers
Same
Shipping
Category.

Step
4b
,
Mitigate
and
Update
Payload
Container
Data
Package
 
If
the
payload
container
headspace
methane
concentration
exceeds
1,250
ppm,
the
payload
container
is
not
eligible
for
shipment
and
must
be
segregated
for
repackaging,
treatment,
or
other
mitigation
measures.
Following
the
completion
of
mitigation
measures,
the
compliance
evaluation
shall
proceed
to
Step
4c
,
"
Start."

Step
4c
,
"
Start"
 
Following
the
completion
and
documentation
of
mitigation
measures
to
ensure
that
the
payload
container
headspace
methane
concentration
is
less
than
or
equal
to
1,250
ppm,
the
compliance
evaluation
shall
start
again
as
described
in
Figure
4.6­
1
and
Section
4.6.2.2.1,
Analytical
Category:
Compliance
with
Flammable
(
Gas/
VOC)
Limits.

Step
4d
,
All
Payload
Containers
Same
Shipping
Category
 
Does
the
payload
container
proposed
belong
to
the
same
shipping
category
as
the
other
containers
proposed
for
payload
assembly?
If
the
payload
container
is
proposed
for
shipment
in
a
payload
assembly
comprised
of
containers
of
different
shipping
categories
and/
or
dunnage
containers,
the
compliance
evaluation
shall
proceed
to
Step
4e
,
MixCat.
If
the
payload
container
is
proposed
for
shipment
in
a
payload
assembly
comprised
of
payload
containers
of
the
same
shipping
category,
the
evaluation
shall
proceed
to
Step
4f
,
Flammable
(
Gas/
VOC)
Concentration
 
Limit.

Step
4e
,
MixCat
 
If
the
payload
container
is
proposed
for
shipment
with
containers
of
different
shipping
categories
and/
or
dunnage
containers,
the
compliance
evaluation
shall
proceed
as
presented
in
Figure
4.6­
5
and
Section
4.6.2.2.5,
Compliance
with
Flammable
(
Gas/
VOC)
Limits
by
Mixing
of
Shipping
Categories
in
a
Payload
Assembly.

Step
4f
,
Flammable
(
Gas/
VOC)
Concentration
 
Limits
 
Is
the
sum
of
flammable
(
gas/
VOC)
concentrations
less
than
or
equal
to
the
MLEL?
The
flammable
gas
concentration
within
the
innermost
layer
of
confinement
of
the
container
must
be
determined
using
the
data
from
the
testing,
as
described
in
Section
4.6.2.5
and
Appendix
3.10
of
the
CH­
TRU
Payload
Appendices.
A
specific
MLEL
must
be
calculated
for
the
container,
as
described
in
HNF­
2600,
REV
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HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
Section
4.6.2.5.
If
the
sum
of
the
flammable
gas
and
VOC
concentrations
exceeds
the
MLEL,
the
container
does
not
comply
with
flammable
(
gas/
VOC)
limits.
Mitigation
measures
must
then
be
taken
under
Step
4g
,
Mitigate
and
Update
Payload
Container
Data
Package.
If
the
flammable
(
gas/
VOC)
concentration
is
less
than
or
equal
to
the
MLEL,
the
flammable
(
gas/
VOC)
limits
are
met,
and
the
compliance
evaluation
is
complete
(
see
Step
4i
,
Payload
Container
Meets
Flammable
(
Gas/
VOC)
Limits).

Step
4g
,
Mitigate
and
Update
Payload
Container
Data
Package
 
If
the
flammable
(
gas/
VOC)
concentration
determined
from
the
testing
exceeds
the
MLEL,
the
container
is
not
eligible
for
shipment
and
must
be
segregated
for
repackaging,
treatment,
or
other
mitigation
measures.
Following
the
completion
of
mitigation
measures,
the
compliance
evaluation
shall
proceed
to
Step
4h
,
"
Start."

Step
4h
,
"
Start"
 
Following
the
completion
and
documentation
of
mitigation
measures,
the
compliance
evaluation
shall
start
again
as
described
in
Figure
4.6­
1
and
Section
4.6.2.2.1,
Analytical
Category:
Compliance
with
Flammable
(
Gas/
VOC)
Limits.

Step
4i
,
Payload
Container
Meets
Flammable
(
Gas/
VOC)
Limits
 
All
containers
reaching
this
step
meet
the
flammable
(
gas/
VOC)
limits
and
are
eligible
for
shipment
if
all
other
transportation
requirements
are
satisfied.

4.6.2.2.5
Compliance
with
Flammable
(
Gas/
VOC)
Limits
by
Mixing
of
Shipping
Categories
in
a
Payload
Assembly
If
the
payload
container
under
evaluation
is
proposed
for
shipment
with
containers
of
different
shipping
categories
and/
or
dunnage
containers
(
as
determined
in
Step
1f
of
Figure
4.6­
1,
Step
3d
of
Figure
4.6­
3,
or
Step
4d
of
Figure
4.6­
4),
the
compliance
with
flammable
(
gas/
VOC)
limits
must
be
evaluated
for
each
container
in
the
payload
assembly.
This
method
accounts
for
the
use
of
dunnage
containers
to
assemble
the
payload.

Figure
4.6­
5
presents
the
logic
for
performing
the
compliance
evaluation
for
flammable
(
gas/
VOC)
limits
for
the
use
of
mixing
of
shipping
categories
in
a
payload
assembly,
which
consists
of
the
following
steps:

Step
5a
,
Data
Packages
for
Containers
in
Proposed
Payload
Assembly
 
The
starting
point
for
compliance
evaluation
for
mixing
of
shipping
categories
in
a
payload
assembly
is
the
data
packages
for
all
payload
containers
proposed
for
inclusion
in
the
payload.

Step
5b
,
Flammability
Index
for
Each
Container
in
Assembly
 
50,000
 
Is
the
flammability
index
(
FI)
for
each
container
proposed
for
inclusion
in
the
payload
assembly
a
non­
negative
number
 
50,000?
For
each
payload
container,
an
FI
must
be
calculated
as
the
ratio
of
the
actual
flammable
gas
generation
rate
to
the
allowable
flammable
gas
generation
rate
limit
multiplied
by
50,000.
Appendix
2.4
of
the
CH­
TRU
Payload
Appendices
describes
the
methodology
for
determining
the
FI
for
payload
assemblies
with
mixed
shipping
categories.
If
the
FI
for
any
payload
container
is
a
negative
number
or
exceeds
50,000,
the
compliance
evaluation
shall
HNF­
2600,
REV
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120
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281
5/
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2005
HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
proceed
to
Step
5c
,
Reconfigure
Payload
Assembly.
If
the
FI
for
each
payload
container
in
the
payload
assembly
is
a
non­
negative
number
less
than
or
equal
to
50,000,
the
flammable
(
gas/
VOC)
limits
are
met
and
the
compliance
evaluation
is
complete
(
see
Step
5h
,
Payload
Container
Meets
Flammable
(
Gas/
VOC)
Limits).

Step
5c
,
Reconfigure
Payload
Assembly
 
Can
the
payload
assembly
be
reconfigured
by
proposing
a
different
combination
of
payload
containers?
If
the
proposed
payload
assembly
cannot
be
reconfigured,
compliance
with
the
flammable
(
gas/
VOC)
limits
cannot
be
met
for
the
proposed
payload
assembly.
Mitigation
measures
must
be
taken
under
Step
5d
,
Mitigate
and
Update
Payload
Container
Data
Package.
If
the
proposed
payload
assembly
can
be
reconfigured
with
a
different
assembly
of
containers,
the
compliance
evaluation
shall
proceed
to
Step
5f
,
Compile
Data
Packages
for
Revised
Payload
Assembly.

Step
5d
,
Mitigate
and
Update
Payload
Container
Data
Package
 
If
the
payload
assembly
cannot
be
reconfigured,
the
payload
is
not
eligible
for
shipment
and
the
payload
containers
exceeding
the
FI
in
the
proposed
payload
assembly
must
be
segregated
for
repackaging,
treatment,
or
other
mitigation
measures.
Following
the
completion
of
mitigation
measures,
the
compliance
evaluation
shall
proceed
to
Step
5e
,
"
Start."

Step
5e
,
"
Start"
 
Following
the
completion
and
documentation
of
mitigation
measures,
the
compliance
evaluation
shall
start
again
as
described
in
Figure
4.6­
1
and
Section
4.6.2.2.1,
Analytical
Category:
Compliance
with
Flammable
(
Gas/
VOC)
Limits.

Step
5f
,
Compile
Data
Packages
for
Revised
Payload
Assembly
 
Following
the
compilation
of
the
data
packages
for
payload
containers
comprising
the
reconfigured
payload
assembly,
the
compliance
evaluation
shall
proceed
to
Step
5g
,
To
Step
5a
Above.

Step
5g
,
To
Step
5a
Above
 
The
evaluation
of
the
reconfigured
payload
assembly
shall
start
again
under
Step
5a
,
Data
Packages
for
Containers
in
Proposed
Payload
Assembly.

Step
5h
,
Payload
Container
Meets
Flammable
(
Gas/
VOC)
Limits
 
All
payload
assemblies
reaching
this
step
meet
the
flammable
(
gas/
VOC)
limits
and
are
eligible
for
shipment
if
all
other
transportation
requirements
are
satisfied.

4.6.2.3
Hydrogen
Gas
Generation
Rate
and
Decay
Heat
Limits
for
Analytical
Category
The
maximum
allowable
hydrogen
gas
generation
rate
limit
and
decay
heat
limit,
which
will
limit
the
concentration
of
hydrogen
gas
within
any
layer
of
confinement
to
less
than
or
equal
to
5%
by
volume,
may
be
determined
for
alpha­
numeric
and
numeric
shipping
categories.
Appendix
2.3
of
the
CH­
TRU
Payload
Appendices
presents
the
methodology
used
for
deriving
the
limits
for
alpha­
numeric
shipping
categories
and
the
derivations
of
the
formulas
used
to
calculate
the
limits
for
numeric
shipping
categories.
Appendix
6.9
of
the
CH­
TRU
Payload
Appendices
describes
the
temperature
dependence
of
hydrogen
gas
generation
and
release
rates.
Appendix
6.10
of
the
CH­
TRU
Payload
Appendices
documents
the
effect
on
decay
heat
limits
of
overpacking
containers.
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Table
4.6.2­
1
lists
the
limits
for
approved
alpha­
numeric
shipping
categories.

For
numeric
shipping
categories
that
do
not
have
a
corresponding
alpha­
numeric
shipping
category
listed
in
Table
4.6.2­
1,
the
procedure
for
determining
limits
is
presented
here.
The
method
for
calculating
the
decay
heat
limit
and
gas
generation
limit
for
numeric
shipping
categories
is
simple
and
conservative
to
provide
a
direct
correlation
between
shipping
category
and
the
limits.

The
numeric
shipping
category
notation
(
as
described
in
Appendix
2.1
of
the
CH­
TRU
Payload
Appendices)
is
in
the
form
of
XX
YYYY
ZZZZ,
where
XX
represents
the
waste
type,
YYYY
represents
the
G
value
(
multiplied
by
100),
and
ZZZZ
represents
the
total
resistance,
RT,
(
divided
by
10,000
and
rounded
up).
The
hydrogen
gas
generation
rate
limit
per
innermost
layer
of
confinement,
CG,
and
the
decay
heat
limit
per
innermost
layer
of
confinement,
Qi,
are
determined
by
the
following
equations:

CG
=
0.05
(
ZZZZ
*
10,000)
sec/
mole
and
Qi
=
(
4824.42)
molecules/
mole
*
watt­
sec/
eV
(
ZZZZ
*
YYYY)
sec­
molecules/
mole­
eV
For
example,
for
shipping
category
10
0040
0160,
substituting
0040
for
YYYY
and
0160
for
ZZZZ
yields:

CG
=
0.05
=
3.125E­
08
mole/
sec
(
0160
*
10,000)
sec/
mole
Qi
=
4824.42
molecules/
mole
*
watt­
sec/
eV
=
0.7538
watts
(
0160
*
0040)
sec­
molecules/
mole­
eV
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Table
4.6.2­
1
­
List
of
Approved
Alpha­
numeric
Shipping
Categories,
Maximum
Allowable
Hydrogen
Gas
Generation
Rates,
and
Maximum
Allowable
Wattages
Numeric
Payload
Shipping
Category
Alpha­
numeric
Payload
Shipping
Category
Maximum
Allowable
Hydrogen
Gas
Generation
Rate
(
moles/
sec)
Maximum
Allowable
Wattage
(
watts)
10
0040
0034
I.
3C0
1.514E­
07
3.6528
10
0040
0147
I.
3A0
3.416E­
08
0.8241
10
0040
0168
I.
3A1
2.980E­
08
0.7189
10
0040
0190
I.
3A2
2.643E­
08
0.6375
10
0040
0207
I.
3B0
2.416E­
08
0.5827
10
0040
0229
I.
3B1
2.189E­
08
0.5281
10
0040
0250
I.
3B2
2.002E­
08
0.4828
10
0040
0648
I.
3A3
7.721E­
09
0.1863
10
0040
0709
I.
3B3
7.061E­
09
0.1703
10
0040
0888
I.
3A4
5.634E­
09
0.1359
10
0040
0949
I.
3B4
5.274E­
09
0.1272
10
0130
0034
I.
2C0
1.514E­
07
1.1240
10
0130
0147
I.
2A0
3.416E­
08
0.2536
10
0130
0168
I.
2A1
2.980E­
08
0.2212
10
0130
0190
I.
2A2
2.643E­
08
0.1962
10
0130
0207
I.
2B0
2.416E­
08
0.1793
10
0130
0229
I.
2B1
2.189E­
08
0.1625
10
0130
0250
I.
2B2
2.002E­
08
0.1486
10
0130
0648
I.
2A3
7.721E­
09
0.0573
10
0130
0709
I.
2B3
7.061E­
09
0.0524
10
0130
0888
I.
2A4
5.634E­
09
0.0418
10
0130
0949
I.
2B4
5.274E­
09
0.0391
10
0160
0034
I.
1C0
1.514E­
07
0.9132
10
0160
0059
I.
1C2
8.598E­
08
0.5185
10
0160
0147
I.
1A0
3.416E­
08
0.2060
10
0160
0168
I.
1A1
2.980E­
08
0.1797
10
0160
0190
I.
1A2
2.643E­
08
0.1594
10
0160
0207
I.
1B0
2.416E­
08
0.1457
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Table
4.6.2­
1
­
List
of
Approved
Alpha­
numeric
Shipping
Categories,
Maximum
Allowable
Hydrogen
Gas
Generation
Rates,
and
Maximum
Allowable
Wattages
(
Continued)

Numeric
Payload
Shipping
Category
Alpha­
numeric
Payload
Shipping
Category
Maximum
Allowable
Hydrogen
Gas
Generation
Rate
(
moles/
sec)
Maximum
Allowable
Wattage
(
watts)
10
0160
0229
I.
1B1
2.189E­
08
0.1320
10
0160
0250
I.
1B2
2.002E­
08
0.1207
10
0160
0286
I.
1C2b
1.751E­
08
0.1056
10
0160
0648
I.
1A3
7.721E­
09
0.0466
10
0160
0709
I.
1B3
7.061E­
09
0.0426
20
0000
0000
II.
2AM
NA
40.0000
20
0000
0000
II.
2BM
NA
40.0000
20
0000
0000
II.
2CM
NA
40.0000
20
0000
0000
II.
2E0
NA
40.0000
20
0170
0028
II.
1C0
1.798E­
07
1.0206
20
0170
0034
II.
1C1f
1.501E­
07
0.8518
20
0170
0039
II.
1C2f
1.288E­
07
0.7309
20
0170
0041
II.
1C1
1.238E­
07
0.7029
20
0170
0043
II.
1C2bf
1.173E­
07
0.6659
20
0170
0049
II.
1C3f
1.039E­
07
0.5897
20
0170
0053
II.
1C2
9.445E­
08
0.5361
20
0170
0067
II.
1D2
7.524E­
08
0.4271
20
0170
0127
II.
1A0
3.966E­
08
0.2251
20
0170
0133
II.
1A1f
3.765E­
08
0.2137
20
0170
0140
II.
1A2af
3.584E­
08
0.2034
20
0170
0143
II.
1A2f
3.519E­
08
0.1997
20
0170
0148
II.
1A1
3.391E­
08
0.1924
20
0170
0152
II.
1A3f
3.303E­
08
0.1875
20
0170
0166
II.
1B0
3.015E­
08
0.1711
20
0170
0169
II.
1A2a
2.961E­
08
0.1680
20
0170
0188
II.
1B1
2.670E­
08
0.1516
20
0170
0209
II.
1B2a
2.396E­
08
0.1360
20
0170
0220
II.
1C2b
2.277E­
08
0.1292
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Table
4.6.2­
1
­
List
of
Approved
Alpha­
numeric
Shipping
Categories,
Maximum
Allowable
Hydrogen
Gas
Generation
Rates,
and
Maximum
Allowable
Wattages
(
Continued)

Numeric
Payload
Shipping
Category
Alpha­
numeric
Payload
Shipping
Category
Maximum
Allowable
Hydrogen
Gas
Generation
Rate
(
moles/
sec)
Maximum
Allowable
Wattage
(
watts)
20
0170
0233
II.
1C3
2.154E­
08
0.1222
20
0170
0327
II.
1A2
1.531E­
08
0.0869
20
0170
0367
II.
1B2
1.364E­
08
0.0774
20
0170
0412
II.
1C4
1.215E­
08
0.0690
20
0170
0506
II.
1A3
9.883E­
09
0.0561
20
0170
0546
II.
1B3
9.163E­
09
0.0520
20
0170
0686
II.
1A4
7.298E­
09
0.0414
20
0170
0725
II.
1B4
6.898E­
09
0.0392
20
0170
0865
II.
1A5
5.785E­
09
0.0328
20
0170
0905
II.
1B5
5.530E­
09
0.0314
20
0170
1044
II.
1A6
4.791E­
09
0.0272
20
0170
1084
II.
1B6
4.616E­
09
0.0262
30
0340
0028
III.
1C0
1.798E­
07
0.5103
30
0340
0034
III.
1C1f
1.501E­
07
0.4259
30
0340
0039
III.
1C2f
1.288E­
07
0.3655
30
0340
0041
III.
1C1
1.238E­
07
0.3515
30
0340
0043
III.
1C2bf
1.173E­
07
0.3329
30
0340
0049
III.
1C3f
1.039E­
07
0.2948
30
0340
0053
III.
1C2
9.445E­
08
0.2680
30
0340
0067
III.
1D2
7.524E­
08
0.2135
30
0340
0127
III.
1A0
3.966E­
08
0.1126
30
0340
0133
III.
1A1f
3.765E­
08
0.1069
30
0340
0140
III.
1A2af
3.584E­
08
0.1017
30
0340
0143
III.
1A2f
3.519E­
08
0.0999
30
0340
0148
III.
1A1
3.391E­
08
0.0962
30
0340
0152
III.
1A3f
3.303E­
08
0.0937
30
0340
0166
III.
1B0
3.015E­
08
0.0856
30
0340
0169
III.
1A2a
2.961E­
08
0.0840
30
0340
0188
III.
1B1
2.670E­
08
0.0758
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Table
4.6.2­
1
­
List
of
Approved
Alpha­
numeric
Shipping
Categories,
Maximum
Allowable
Hydrogen
Gas
Generation
Rates,
and
Maximum
Allowable
Wattages
(
Continued)

Numeric
Payload
Shipping
Category
Alpha­
numeric
Payload
Shipping
Category
Maximum
Allowable
Hydrogen
Gas
Generation
Rate
(
moles/
sec)
Maximum
Allowable
Wattage
(
watts)
30
0340
0209
III.
1B2a
2.396E­
08
0.0680
30
0340
0220
III.
1C2b
2.277E­
08
0.0646
30
0340
0233
III.
1C3
2.154E­
08
0.0611
30
0340
0327
III.
1A2
1.531E­
08
0.0434
30
0340
0367
III.
1B2
1.364E­
08
0.0387
30
0340
0412
III.
1C4
1.215E­
08
0.0345
30
0340
0506
III.
1A3
9.883E­
09
0.0280
30
0340
0546
III.
1B3
9.163E­
09
0.0260
30
0340
0686
III.
1A4
7.298E­
09
0.0207
30
0340
0725
III.
1B4
6.898E­
09
0.0196
30
0340
0865
III.
1A5
5.785E­
09
0.0164
30
0340
0905
III.
1B5
5.530E­
09
0.0157
30
0340
1044
III.
1A6
4.791E­
09
0.0136
30
0340
1084
III.
1B6
4.616E­
09
0.0131
40
9999
0127
IV.
1A0T
3.937E­
08
7.0000
40
9999
0148
IV.
1A1T
3.378E­
08
7.0000
40
9999
0169
IV.
1A2T
2.959E­
08
7.0000
40
9999
0188
IV.
1B1T
2.660E­
08
7.0000
40
9999
0209
IV.
1B2T
2.392E­
08
7.0000
40
9999
0506
IV.
1A3T
9.881E­
09
7.0000
40
9999
0546
IV.
1B3T
9.158E­
09
7.0000
4.6.2.4
Drum
Age
Criteria
Introduction
If
a
concentration
of
flammable
VOCs
in
the
payload
container
headspace
of
less
than
or
equal
to
500
ppm
cannot
be
established
based
on
waste
generation
procedures
or
records
of
process
knowledge,
headspace
gas
sampling
for
flammable
VOCs
is
required.
Prior
to
performing
headspace
sampling,
DACs
need
to
be
met
for
headspace
samples
to
be
valid
and
is
performed
in
accordance
with
WMP­
400,
Section
7.1.8.
DACs
are
estimates
of
time
required
for
VOCs
in
a
payload
container
to
reach
90
percent
of
the
equilibrium
steady­
state
concentration
within
the
different
layers
of
confinement.
Alternately,
the
headspace
sample
taken
before
the
DAC
has
been
met
can
be
used
to
determine
the
90%
steady­
state
concentration
in
a
waste
container.
The
90%
steady­
state
concentration
can
then
be
correlated
to
the
VOC
concentration
in
the
innermost
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layer
of
confinement
by
the
use
of
prediction
factors
(
PFs),
which
are
multipliers
to
be
applied
to
the
headspace
concentration.
The
method
used
for
determining
the
steady­
state
(
90%)
VOC
concentration
from
DACs
(
or
measurement)
and
PFs
is
based
on
Liekhus
et
al.,
October
2000.2
Three
options
are
available:

Option
1
No
DACs
Required.
If
the
concentration
of
flammable
VOCs
in
a
payload
container
can
be
shown
to
be
less
than
or
equal
to
500
ppm
from
the
waste
generation
procedures
or
records
of
process
knowledge,
then
no
DACs
or
PFs
are
required.
If
the
concentration
of
flammable
VOCs
cannot
be
determined
from
the
waste
generation
procedures
or
the
records
of
process
knowledge,
headspace
sampling
must
be
performed
and
Option
2
or
Option
3
below
must
be
used.

Option
2
Assignment
of
DACs
for
Common
Packaging
Configurations.
DACs
for
common
representative
packaging
configurations
used
for
CH­
TRU
waste
at
the
sites
are
presented
in
look­
up
tables.
Under
Option
2,
there
are
three
container
venting
and
sampling
scenarios.
Option
2
and
the
associated
scenarios
and
look­
up
tables
are
discussed
in
detail
in
Section
Section
4.6.2.4
under
Assignment
of
DACs
for
Common
Packaging
Configurations.
DACs
are
determined
and
documented
using
WMP­
400,
Section
7.1.8.

Option
3
Calculation
of
Steady­
State
VOC
Concentrations
for
Specific
Packaging
Configurations.
For
specific
packaging
configurations
not
covered
by
Option
2,
the
steady­
state
VOC
concentration
can
be
determined
based
on
sampling
(
measurement)
using
the
methodology
described
in
Liekhus
et
al.,
October
2000.2
Option
3
is
described
in
Appendix
3.9
of
the
CH­
TRU
Payload
Appendices.

Figure
4.6.2­
3
presents
a
flowchart
for
determining
the
appropriate
option.
A
list
of
flammable
VOCs
identified
by
the
sites
in
CH­
TRU
waste
is
provided
as
Table
4.6.2­
2.
If
additional
flammable
VOCs
(
i.
e.,
not
listed
in
Table
4.6.2­
2)
are
identified
in
concentrations
greater
than
500
ppm
total,
Section
4.6.2.5,
under
Determine
Concentration
of
Flammable
VOCs
Using
PFs,
specifies
a
formalized
process
for
including
these
VOCs
in
the
analysis
for
compliance
with
the
flammable
(
gas/
VOC)
limits.

2
Liekhus,
K.
J.,
S.
M.
Djordjevic,
M.
Devarakonda,
M.
J.
Connolly,
October
2000,
"
Determination
of
Drum
Age
Criteria
and
Prediction
Factors
Based
on
Packaging
Configurations,"
INEEL/
EXT­
2000­
01207,
Idaho
National
Engineering
and
Environmental
Laboratory,
Idaho
Falls,
Idaho.
HNF­
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HANFORD
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Is
packaging
configuration
bounded
by
packaging
configurations
in
Table
5.2­
3?

Has
WIPP
CH­
TRU
Payload
Engineer
determined
and
approved
DAC
for
new
packaging
configuration?

843102.01020000
A9
Is
flammable
VOCs
concentration
500
ppm
(
based
on
Process
Knowledge)?

Determine
container
venting
and
sampling
scenario
Option
1:
Drum
Age
Criteria
do
not
apply.
VOC
Headspace
sampling
not
required.
Yes
No
Yes
Yes
Yes
No
No
No
Option
2:
Drum
Age
Criteria
assigned
based
on
packaging
configuration
Start
Request
WIPP
CH­
TRU
Payload
Engineer
determination
of
DAC
for
new
packaging
configuration.

Option
3:
Steady
state
flammable
VOC
concentration
calculated
from
sample
taken
after
container
packaged
using
VOC
concentration
multipliers
Waste
may
not
be
shipped.
Are
additional
flammable
VOCs
identified
in
concentrations
>
500
ppm
total?

Has
WIPP
CH­
TRU
Payload
Engineer
performed
evaluation
and
categorized
additional
VOCs
per
Section
5.2.5.3.2?
Yes
No
No
Yes
Scenario
3
Drum
Vented
at
Generation
and
Sampled
Sometime
Later.

Wait
until
DAC
3
from
Table
5.2­
7
or
Table
5.2­
8
has
been
satisfied
before
sampling
(
time
from
waste
packaging
to
headspace
sampling).
Scenario
2
Drum
Vented
Sometime
After
Generation
and
Sampled
Sometime
Later.

Wait
until
DAC
1
from
Table
5.2­
4
has
been
satisfied
before
venting
(
time
from
waste
container
closure
to
time
of
venting);
after
venting
wait
until
DAC2
from
Table
5.2­
5
or
5.2­
6
has
been
satisfied
before
sampling
(
time
from
container
venting
to
headspace
sampling).
Scenario
1
Drum
Vented
and
Sampled
(
Under
Liner
Lid)
Sometime
After
Generation.

Wait
until
DAC
1
from
Table
5.2­
4
has
been
satisfied
before
venting
and
sampling
(
time
from
container
closure
to
time
of
venting
and
sampling).
Submit
information
to
WIPP
CH­
TRU
Payload
Engineer
for
evaluation.

Has
WIPP
CH­
TRU
Payload
Engineer
determined
and
approved
concentration
multipliers
for
new
packaging
configuration?
Request
WIPP
CH­
TRU
Payload
Engineer
determination
of
concentration
multipliers
for
new
packaging
configuration.

Yes
No
Is
packaging
configuration
covered
by
configurations
for
Option
3?

Figure
4.6.2­
3
 
Determination
of
DAC
Option
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CERTIFICATION
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Table
4.6.2­
2
 
List
of
Flammable
Volatile
Organic
Compounds
Identified
by
Sites
in
CH­
TRU
Wastesa
Acetone
Benzene
1­
Butanol
Chlorobenzene
Cyclohexane
1,1­
Dichloroethane
1,2­
Dichloroethane
1,1­
Dichloroethene
cis­
1,2­
Dichloroethene
Ethyl
benzene
Ethyl
ether
Methanol
Methyl
ethyl
ketone
Methyl
isobutyl
ketone
Toluene
1,2,4­
Trimethylbenzene
1,3,5­
Trimethylbenzene
Xylenes
aIf
additional
flammable
VOCs
are
identified
in
concentrations
greater
than
500
ppm
total,
the
methodology
documented
in
Section
4.6.2.5
under
Determine
Concentration
of
Flammable
VOCs
Using
PFs
shall
be
used.

Assignment
of
DACs
for
Common
Packaging
Configurations
The
derivation
of
the
DACs
for
Option
2
is
based
on
specific
packaging
configurations
and
waste
types
commonly
used
at
the
TRU
waste
sites.
Considering
only
the
number
of
layers
of
confinement,
the
common
packaging
configurations
currently
described
in
the
CH­
TRUCON
document1
can
be
bound
by
the
packaging
configurations
presented
in
Table
4.6.2­
3.

For
example,
a
packaging
configuration
consisting
of
a
single
plastic
bag
in
a
55­
gallon
drum
for
Waste
Type
II
or
III
could
be
conservatively
placed
into
Configuration
2
(
i.
e.,
the
DAC
for
a
packaging
configuration
consisting
of
1
inner
bag
would
be
less
than
or
equal
to
that
for
3
inner
bags
and
1
liner
bag).
Similarly,
a
configuration
of
2
inner
bags
and
2
liner
bags
in
a
55­
gallon
drum
for
these
waste
types
would
be
assigned
to
Configuration
3.
In
addition,
filtered
bag
layers
are
also
conservatively
assigned
to
the
configurations
in
Table
4.6.2­
3.
For
example,
a
configuration
of
Waste
Type
II
with
3
filtered
inner
bags
and
1
filtered
liner
bag
in
a
55­
gallon
drum
is
bounded
by
Packaging
Configuration
2.
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CERTIFICATION
PLAN
Table
4.6.2­
3
 
Common
CH­
TRU
Waste
Packaging
Configurations
Packaging
Configuration
Waste
Types
II
and
III
Waste
Types
I
and
IV
Packaging
Configuration
1
(
55­
gallon
drums)
No
inner
bags,
no
liner
bags
Packaging
Configuration
2
(
55­
gallon
drums)
Up
to
4
bag
layers,
up
to
1
of
which
is
a
liner
bag
Any
configuration
with
1
liner
bag
Packaging
Configuration
3
(
55­
gallon
drums)
Up
to
6
bag
layers,
up
to
2
of
which
are
liner
bags
Any
configuration
with
2
liner
bags
Packaging
Configuration
4
(
pipe
components)
Up
to
2
inner
bags
and
1
filtered
metal
can
inside
a
pipe
component
(
headspace
sample
taken
inside
the
pipe
component)
Packaging
Configuration
5
(
SWBs
and
TDOPs)
SWB
or
TDOP
with
up
to
1
bag
layer
(
inner
or
liner)

Packaging
Configuration
6
(
SWBs
and
TDOPs)
SWB
or
TDOP
with
up
to
6
bag
layers,
up
to
1
of
which
is
a
liner
bag
Packaging
Configuration
7
(
85­
gallon
drums)
85­
gallon
drum
with
filtered
inner
lid
(
no
inner
or
liner
bags
and
no
rigid
liners)

For
Waste
Types
I
and
IV
in
55­
gallon
drums,
one
or
two
liner
bags
are
the
configurations
most
commonly
used.
The
DAC
analysis
conservatively
assumes
for
solidified
wastes
that
only
the
top
of
the
liner
bag
is
available
for
VOC
transport.
The
presence
of
inner
bags
makes
the
entire
liner
bag
area
available
and
hence
the
DACs
are
bound
by
the
configurations
in
Table
4.6.2­
3.2
Any
site
requiring
the
transportation
of
TRU
waste
in
the
TRUPACT­
II
or
HalfPACT
that
cannot
be
covered
under
a
packaging
configuration
included
in
Table
4.6.2­
3
must
request
the
determination
of
an
appropriate
DAC
by
submitting
a
request
in
writing
to
the
WIPP
CH­
TRU
Payload
Engineer.

The
WIPP
CH­
TRU
Payload
Engineer
shall
assign
a
conservative
DAC
for
a
packaging
configuration
not
covered
under
Table
4.6.2­
3
using
the
governing
equations
and
methodology.
2,3
Compliance
with
all
other
transportation
requirements
of
the
CH­
TRAMPAC
document
shall
also
be
demonstrated.
The
WIPP
CH­
TRU
Payload
Engineer
does
not
have
the
authority
to
change
the
transportation
requirements
for
the
TRUPACT­
II
as
specified
in
the
CH­
TRAMPAC
document
without
approval
from
the
NRC.
Section
4.1
describes
the
process
for
WIPP
CH­
TRU
Payload
Engineer
approval
of
new
packaging
configurations
as
part
of
the
TRUCON
code
approval
process.

DACs
are
defined
for
three
unique
venting
and
sampling
scenarios.
These
venting
and
sampling
scenarios
are
defined
by
the
time
elapsed
after
container
closure
and
venting,
as
follows:

t1
=
time
(
days)
elapsed
after
container
closure
until
venting
t2
=
time
(
days)
elapsed
after
venting.
HNF­
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HANFORD
SITE
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WASTE
CERTIFICATION
PLAN
Scenario
1:
The
drum
liner
headspace
(
under
liner
lid)
can
be
sampled
at
the
time
of
venting
if
t1
is
greater
than
DAC1.
The
drum
age
criterion
DAC1
is
defined
as
the
time
for
a
representative
VOC
to
reach
a
concentration
of
at
least
90%
of
its
equilibrium
concentration
before
drum
venting.
Table
4.6.2­
4
presents
the
DAC1
values.

Table
4.6.2­
4
 
DAC1
Values
(
in
Days)

Waste
Type
DAC1
(
days)
Waste
Types
I
and
IV
127
Waste
Types
II
and
III
53
Scenario
2:
For
drums
generated
in
an
unvented
condition
and
subsequently
vented,
the
drum
headspace
can
be
sampled
in
a
vented
drum
if
t1
is
greater
than
DAC1
and
t2
is
greater
than
DAC2.

The
drum
age
criterion
DAC2
is
defined
as
the
time
for
a
representative
VOC
to
reach
a
headspace
concentration
of
at
least
90%
of
its
steady­
state
concentration
after
venting
a
waste
drum
that
was
unvented
for
at
least
DAC1.
DAC2
values
are
calculated
for
the
two
categories
of
waste
types
under
Scenario
1
with
four
different
opening
sizes
in
the
punctured
drum
liner
lid
and
three
different
drum
filter
diffusivities.

In
other
words,
under
this
scenario,
if
the
drum
has
remained
in
an
unvented
condition
for
a
period
of
at
least
53
days
for
Waste
Types
II
and
III
and
127
days
for
Waste
Types
I
and
IV,
equilibration
of
VOCs
is
complete
inside
the
drum.
When
the
drum
is
subsequently
vented,
a
time
period
for
the
appropriate
DAC2
listed
in
Table
4.6.2­
5
or
4.6.2­
6
is
needed
before
sampling
to
ensure
reequilibration
between
the
liner
and
the
drum
headspace.

Table
4.6.2­
5
 
Packaging­
Specific
DAC2
Values
(
in
Days)
for
Solidified
Waste
(
Waste
Types
I
and
IV)

Liner
Lid
Opening
Drum
Filter
Minimum
Hydrogen
Diffusivity
(
m/
s/
mf)
0.3­
inch
Diameter
Hole
0.375­
inch
Diameter
Hole
0.75­
inch
Diameter
Hole
1­
inch
Diameter
Hole
1.9
x
10­
6
36
30
23
22
3.7
x
10­
6
30
25
19
18
3.7
x
10­
5
13
11
11
11
m/
s/
mf
=
mole
per
second
per
mole
fraction.
HNF­
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Table
4.6.2­
6
 
Packaging­
Specific
DAC2
Values
(
in
Days)
for
Solid
Waste
(
Waste
Types
II
and
III)

Liner
Lid
Opening
Drum
Filter
Minimum
Hydrogen
Diffusivity
(
m/
s/
mf)
0.3­
inch
Diameter
Hole
0.375­
inch
Diameter
Hole
0.75­
inch
Diameter
Hole
1­
inch
Diameter
Hole
1.9
x
10­
6
29
22
13
12
3.7
x
10­
6
25
20
12
11
3.7
x
10­
5
7
6
6
4
m/
s/
mf
=
mole
per
second
per
mole
fraction.

Scenario
3:
If
t1
is
less
than
DAC1
when
the
container
is
vented,
the
container
headspace
can
be
sampled
when
t2
is
greater
than
DAC3.
Also,
for
newly
generated
payload
containers
that
were
vented
at
the
time
of
generation,
the
container
headspace
can
be
sampled
after
DAC3
has
been
exceeded.

The
drum
age
criterion
DAC3
is
defined
as
the
time
for
a
representative
VOC
to
reach
a
headspace
concentration
of
at
least
90%
of
its
steady­
state
concentration.
DAC3
values
are
calculated
for
the
two
categories
of
waste
types
each
with
different
packaging
configurations,
different
opening
sizes
in
the
drum
liner
lid
as
well
as
the
case
of
no
rigid
liner
inside
the
drum,
and
different
filter
diffusivities.
The
appropriate
DAC3
values
are
listed
in
Tables
4.6.2­
7
and
4.6.2­
8.

Because
direct
load
TDOPs
are
equipped
with
a
greater
number
of
filters
than
SWBs,
the
SWB
packaging
configurations
(
Packaging
Configurations
5
and
6)
bound
the
direct
load
TDOP
packaging
configurations.

Packaging
Configuration
7
describes
85­
gallon
drums
with
a
vented
inner
lid
and
no
additional
inner
layers
of
confinement
and
no
rigid
liners.
Sampling
is
performed
between
the
inner
and
outer
lids
or
inside
the
inner
lid.
The
DAC
values
for
an
85­
gallon
drum
with
no
additional
inner
layers
of
confinement
and
no
rigid
liner
are
listed
in
Tables
5.2­
7
and
5.2­
8.
HNF­
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HANFORD
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CERTIFICATION
PLAN
Table
4.6.2­
7
 
Packaging­
Specific
DAC3
Values
(
in
Days)
for
Solidified
Waste
(
Waste
Types
I
and
IV)

Packaging
Configuration
1
Liner
Lid
Opening
Drum
Filter
Minimum
Hydrogen
Diffusivity
(
m/
s/
mf)
0.3­
inch
Diameter
Hole
0.375­
inch
Diameter
Hole
0.75­
inch
Diameter
Hole
1­
inch
Diameter
Hole
No
Lid
No
Liner
1.9
x
10­
6
131
95
37
24
4
4
3.7
x
10­
6
111
85
36
24
4
4
3.7
x
10­
5
28
28
23
19
4
4
Packaging
Configuration
2
Liner
Lid
Opening
Drum
Filter
Minimum
Hydrogen
Diffusivity
(
m/
s/
mf)
0.3­
inch
Diameter
Hole
0.375­
inch
Diameter
Hole
0.75­
inch
Diameter
Hole
1­
inch
Diameter
Hole
No
Lid
No
Liner
1.9
x
10­
6
213
175
108
92
56
18
3.7
x
10­
6
188
161
105
90
56
17
3.7
x
10­
5
80
80
75
71
49
10
Packaging
Configuration
3
Liner
Lid
Opening
Drum
Filter
Minimum
Hydrogen
Diffusivity
(
m/
s/
mf)
0.3­
inch
Diameter
Hole
0.375­
inch
Diameter
Hole
0.75­
inch
Diameter
Hole
1­
inch
Diameter
Hole
No
Lid
No
Liner
1.9
x
10­
6
283
243
171
154
107
34
3.7
x
10­
6
253
225
166
151
106
31
3.7
x
10­
5
121
121
115
110
84
13
Packaging
Configuration
4
Pipe
Component
Filter
Minimum
Hydrogen
Diffusivity
(
m/
s/
mf)
Headspace
Sample
Taken
Inside
Pipe
Component
1.9
x
10­
6
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Table
4.6.2­
7
 
Packaging­
Specific
DAC3
Values
(
in
Days)
for
Solidified
Waste
(
Waste
Types
I
and
IV)
(
Continued)

Packaging
Configuration
5
Minimum
Total
Filter
Diffusivity
(
m/
s/
mf)
Headspace
Sample
Taken
Inside
Direct
Load
SWB/
TDOP
7.4
x
10­
6
(
SWB)
15
3.3
x
10­
5
(
TDOP)
15
Packaging
Configuration
6
Minimum
Total
Filter
Diffusivity
(
m/
s/
mf)
Headspace
Sample
Taken
Inside
Direct
Load
SWB/
TDOP
7.4
x
10­
6
(
SWB)
56
3.3
x
10­
5
(
TDOP)
56
Packaging
Configuration
7a
Inner
Lid
Filter
Vent
Minimum
Hydrogen
Diffusivity
(
m/
s/
mf)
Drum
Filter
Minimum
Hydrogen
Diffusivity
(
m/
s/
mf)
7.4
x
10­
6
1.85
x
10­
5
9.25
x
10­
5
3.7
x
10­
6
13
7
2
7.4
x
10­
6
10
6
2
1.85
x
10­
5
6
4
2
aHeadspace
sample
taken
between
inner
and
outer
drum
lids.
If
headspace
sample
is
taken
inside
the
filtered
inner
drum
lid
prior
to
placement
of
the
outer
drum
lid,
then
a
DAC3
value
of
2
days
may
be
used.
m/
s/
mf
=
mole
per
second
per
mole
fraction.
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HANFORD
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PLAN
Table
4.6.2­
8
 
Packaging­
Specific
DAC3
Values
(
in
Days)
for
Solid
Waste
(
Waste
Types
II
and
III)

Packaging
Configuration
1
Liner
Lid
Opening
Drum
Filter
Minimum
Hydrogen
Diffusivity
(
m/
s/
mf)
0.3­
inch
Diameter
Hole
0.375­
inch
Diameter
Hole
0.75­
inch
Diameter
Hole
1­
inch
Diameter
Hole
No
Lid
No
Liner
1.9
x
10­
6
131
95
37
24
4
4
3.7
x
10­
6
111
85
36
24
4
4
3.7
x
10­
5
28
28
23
19
4
4
Packaging
Configuration
2
Liner
Lid
Opening
Drum
Filter
Minimum
Hydrogen
Diffusivity
(
m/
s/
mf)
0.3­
inch
Diameter
Hole
0.375­
inch
Diameter
Hole
0.75­
inch
Diameter
Hole
1­
inch
Diameter
Hole
No
Lid
No
Liner
1.9
x
10­
6
175
138
75
60
30
11
3.7
x
10­
6
152
126
73
59
30
11
3.7
x
10­
5
58
57
52
47
28
8
Packaging
Configuration
3
Liner
Lid
Opening
Drum
Filter
Minimum
Hydrogen
Diffusivity
(
m/
s/
mf)
0.3­
inch
Diameter
Hole
0.375­
inch
Diameter
Hole
0.75­
inch
Diameter
Hole
1­
inch
Diameter
Hole
No
Lid
No
Liner
1.9
x
10­
6
199
161
96
80
46
16
3.7
x
10­
6
175
148a
93
79
46
16
3.7
x
10­
5
72
72
67
62
42
10
Packaging
Configuration
4
Pipe
Component
Filter
Minimum
Hydrogen
Diffusivity
(
m/
s/
mf)
Headspace
Sample
Taken
Inside
Pipe
Component
1.9
x
10­
6
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SITE
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WASTE
CERTIFICATION
PLAN
Table
4.6.2­
8
 
Packaging­
Specific
DAC3
Values
(
in
Days)
for
Solid
Waste
(
Waste
Types
II
and
III)
(
Continued)

Packaging
Configuration
5
Minimum
Total
Filter
Diffusivity
(
m/
s/
mf)
Headspace
Sample
Taken
Inside
Direct
Load
SWB/
TDOP
7.4
x
10­
6
(
SWB)
15
3.3
x
10­
5
(
TDOP)
15
Packaging
Configuration
6
Minimum
Total
Filter
Diffusivity
(
m/
s/
mf)
Headspace
Sample
Taken
Inside
Direct
Load
SWB/
TDOP
7.4
x
10­
6
(
SWB)
56
3.3
x
10­
5
(
TDOP)
56
Packaging
Configuration
7b
Inner
Lid
Filter
Vent
Minimum
Hydrogen
Diffusivity
(
m/
s/
mf)
Drum
Filter
Minimum
Hydrogen
Diffusivity
(
m/
s/
mf)
7.4
x
10­
6
1.85
x
10­
5
9.25
x
10­
5
3.7
x
10­
6
13
7
2
7.4
x
10­
6
10
6
2
1.85
x
10­
5
6
4
2
aDAC
of
142
days
is
applicable
provided
that
the
packaging
configuration
does
not
exceed
3
inner
bags
and
2
liner
bags.
This
DAC
value
for
this
bounding
packaging
configuration
has
been
previously
used
to
address
headspace
sampling
issues
at
the
sites
for
disposal
purposes.
2
bHeadspace
sample
taken
between
inner
and
outer
drum
lids.
If
headspace
sample
is
taken
inside
the
filtered
inner
drum
lid
prior
to
placement
of
the
outer
drum
lid,
then
a
DAC3
value
of
2
days
may
be
used.
m/
s/
mf
=
mole
per
second
per
mole
fraction.
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HANFORD
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CERTIFICATION
PLAN
4.6.2.5
United
Flammable
Gas
Test
Procedure
Introduction
CH­
TRU
wastes
to
be
transported
in
the
TRUPACT­
II
packages
fall
into
one
of
two
categories
based
on
their
gas
generation
potential
 
"
analytical
category
waste"
or
"
test
category
waste."
The
wastes
that
can
be
qualified
for
shipment
based
on
decay
heat
limits
derived
from
theoretical
worst­
case
calculations
of
gas
generation
potential
comprise
the
"
analytical
category."
The
CHTRU
waste
containers
that
exceed
the
applicable
decay
heat
limits
set
for
the
analytical
category,
or
that
exceed
500
ppm
of
flammable
VOCs
in
the
headspace,
or
that
do
not
have
an
established
theoretical
bounding
gas
generation
rate
(
G
value),
belong
in
the
"
test
category."
The
Unified
Flammable
Gas
Test
Procedure
(
UFGTP)
details
the
methodology
used
to
evaluate
compliance
of
test
category
wastes
with
flammable
(
gas/
VOC)
limits.

Purpose
This
UFGTP
provides
the
technical
basis
for
determining
whether
a
test
category
payload
container
demonstrates
compliance
with
the
flammable
(
gas/
VOC)
limits.
It
also
provides
instructions
for
the
methodology
by
which
each
test
activity
will
be
performed.
The
first,
or
short­
term,
objective
of
the
UFGTP
is
to
facilitate
shipment
of
waste
in
the
test
category
by
testing
individual
payload
containers
to
show
compliance
with
the
flammable
gas
generation
and
concentration
requirements.
The
second,
or
long­
term,
objective
is
to
improve
waste
shipability
for
specific
populations
or
subpopulations
of
waste
by
arriving
at
more
realistic
gas
generation
rates
based
on
the
results
of
measurement
and
testing
(
Hanford
is
not
implementing
this
testing
method
at
this
time).
The
process
for
implementation
of
the
long­
term
objective
is
defined
in
the
"
UFGTP
Long­
Term
Objective
Implementation
Method"
3
and
described
in
Section
4.6.2.5
under
Determine
Compliance
with
Flammable
Gas
Generation
Rate
Limit.

Applicability
This
procedure
applies
to
individual
containers
of
CH­
TRU
waste
that
fall
into
the
test
category.
Containers
are
placed
into
the
test
category
if
they
fall
into
one
of
the
following
classifications.

 
The
decay
heat
loading
of
the
waste
container
exceeds
the
analytical
category
decay
heat
limit
for
the
shipping
category
of
that
payload
container
and
the
total
concentration
of
potentially
flammable
VOCs
within
the
container
headspace
is
less
than
or
equal
to
500
ppm.
Payload
containers
in
Waste
Types
I
(
10),
II
(
20),
and
III
(
30)
belong
in
this
category.
 
The
total
concentration
of
potentially
flammable
VOCs
within
the
container
headspace
exceeds
500
ppm.
Payload
containers
in
Waste
Type
I
(
10),
II
(
20),
and
III
(
30)
belong
in
this
category.

3
Shaw
Environmental
&
Infrastructure,
Inc.,
current
version,
"
UFGTP
Long­
Term
Objective
Implementation
Methodology,"
Shaw
Environmental
&
Infrastructure,
Inc.,
Albuquerque,
New
Mexico.
HNF­
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HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
 
A
waste
process
does
not
have
a
fully
characterized
bounding
G
value
from
previous
sampling
or
waste
stream
analysis.
Payload
containers
in
Waste
Type
IV
(
40)
belong
to
this
category.
Hanford
is
not
shipping
waste
type
IV
(
40)
at
this
time.

Summary
of
Procedure
The
UFGTP
details
the
method
used
to
evaluate
the
compliance
of
test
category
wastes
with
flammable
(
gas/
VOC)
rate
and
concentration
limits.
As
described
in
Section
4.6.1.2
of
this
document,
the
evaluation
of
compliance
of
test
category
wastes
with
the
limits
is
carried
out
through
the
use
of
one
of
two
methods:

 
Measurement
 
Testing.

The
procedure
outlined
in
this
document
is
valid
to
show
compliance
on
a
per
container
basis
assuming
that
each
container
will
be
assembled
into
a
payload
with
payload
containers
belonging
to
the
same
payload
shipping
category,
as
defined
in
Section
4.6.1
of
this
document.
Compliance
evaluation
requirements
for
payloads
with
multiple
shipping
categories
and/
or
dunnage
containers
are
described
in
Sections
4.7.1.2
of
this
document.
Data
obtained
from
this
procedure
may
be
used
in
the
mixing
methodology
for
compliance
with
flammable
(
gas/
VOC)
limits
described
in
Section
4.7.4
and
the
evaluation
for
compliance
with
payload
total
gas
release
rate
limits
described
in
Section
4.7.1.

Hanford
is
only
implementing
the
measurement
evaluation
method
and
relies
on
WWIS
for
UFGTP
calculations.
Information
is
entered
into
WWIS
using
WMP­
400,
Section
7.1.5.

Measurement
This
consists
of
using
a
headspace
gas
measurement
(
taken
under
the
container
lid,
liner
lid,
or
pipe
component
lid)
along
with
the
waste
packaging
configuration
and
history
of
the
container
to
demonstrate
compliance
with
flammable
(
gas/
VOC)
limits.
This
is
applicable
to
test
category
wastes
of
Waste
Types
I,
II,
and
III
that
exceed
decay
heat
limits
and/
or
exceed
500
ppm
flammable
VOCs
in
the
headspace
of
the
payload
container.
The
headspace
concentrations
of
the
flammable
gases
and
the
time
history
of
the
payload
containers
are
used
to
determine
the
gas/
VOC
concentrations
in
the
innermost
confinement
layer.
The
flammable
gas
generation
rates
are
determined
from
these
measured
concentrations
using
analytical
solutions
as
discussed
in
Appendix
3.10
of
the
CH­
TRU
Payload
Appendices.

The
headspace
flammable
(
gas/
VOC)
concentrations
are
also
used
to
determine
compliance
with
the
MLEL
as
discussed
in
Appendix
3.10
of
the
CH­
TRU
Payload
Appendices.
The
headspace
concentrations
of
methane
are
evaluated
for
compliance
with
the
screening
limit
of
1,250
ppm.
Compliance
with
the
allowable
flammable
(
gas/
VOC)
concentrations
using
headspace
gas
measurement
is
described
in
detail
in
Section
4.6.2.5
under
Procedure
for
Measurement.

For
all
containers,
flammable
(
gas/
VOC)
concentrations
may
be
measured
in
an
inner
layer
of
confinement
rather
than
the
payload
container
headspace.
HNF­
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2005
HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
If
the
headspace
of
the
outermost
(
overpacking)
payload
container
of
an
overpacked
configuration
with
multiple
containers
(
drums
in
an
SWB)
is
measured,
the
packaging
configuration
must
be
described
as
a
direct
load
configuration
in
order
to
apply
the
limits
specified
in
this
section.

Testing
Hanford
is
not
implementing
testing
at
this
time.

Procedure
for
Measurement
Compliance
with
transportation
requirements
through
either
measurement
or
testing
shall
either
be
documented
on
the
CH­
TRU
Waste
Test
Category
Payload
Container
Data
Sheet
(
the
Data
Sheet)
(
Appendix
B­
3)
or
shall
be
compiled
through
the
use
of
a
verified/
validated
software
package
based
on
the
method
presented
in
this
section
and
in
Appendix
3.10
of
the
CH­
TRU
Payload
Appendices.
If
documented
manually,
Test
Category
Payload
Container
Datasheet
in
Appendix
B­
3
may
be
reformatted
for
site
purposes,
but
all
information
on
the
data
sheet
shall
be
retained.
If
sections
of
the
data
sheet
are
not
applicable,
mark
as
such
(
e.
g.,
"
not
applicable"
or
"
NA").
Record
the
identification
parameters
identified
in
Section
1
of
the
Data
Sheet
prior
to
proceeding
to
the
other
sections.

If
a
verified/
validated
software
package
is
used,
the
necessary
data
shall
be
input
and
recorded
to
assess
transportation
compliance
and
the
Test
Category
Payload
Container
Datasheet
in
Appendix
B­
3
need
not
be
completed.

The
compliance
evaluation
for
flammable
(
gas/
VOC)
limits
by
measurement
is
as
described
below:

Determine
Compliance
with
Methane
Screening
Limit
1.
Determine
the
headspace
concentration
of
methane.
The
headspace
measurement
methods
and
the
associated
QA
requirements
are
discussed
in
the
Quality
Assurance
Program
Plan
(
QAPP)
for
the
TRUPACT­
II
Gas
Generation
Test
Program.
4
2.
Record
the
location
of
methane
measurement
(
container
headspace
or
inside
the
rigid
drum
liner,
if
applicable),
the
date
of
methane
measurement
(
if
applicable),
and
the
determined
concentration
of
methane
(
see
Section
2
of
the
Data
Sheet).

4
U.
S.
Department
of
Energy
(
DOE),
"
Quality
Assurance
Program
Plan
for
TRUPACT­
II
Gas
Generation
Test
Program,"
DOE/
WIPP
01­
3187,
current
revision,
U.
S.
Department
of
Energy,
Carlsbad
Field
Office,
Carlsbad,
New
Mexico.
HNF­
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HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
3.
Compare
the
methane
concentration
to
the
1,250
ppm
screening
limit.
Indicate
on
the
Data
Sheet
by
(
Yes/
No)
if
the
methane
concentration
is
less
than
or
equal
to
1,250
ppm.
(
The
rationale
for
the
methane
screening
limit
is
provided
below.)

Position:
A
methane
screening
limit
or
concentration
of
1,250
ppm
in
the
container
headspace
should
be
used
in
flammability
evaluations.
If
the
container
headspace
methane
concentration
is
below
this
screening
limit,
the
concentration
of
methane
should
be
added
to
the
hydrogen
concentration
and
the
flammable
gas
generation
rate
should
be
determined.
If
the
concentration
is
above
the
screening
limit,
the
container
is
not
eligible
for
shipment
and
the
container
shall
be
either
repackaged
or
mitigation
measures
shall
be
adopted.

Rationale:
Although
the
term
"
flammable
gases"
includes
both
hydrogen
and
methane,
gas
measurement
data
suggest
methane
is
either
not
present
or
is
present
in
very
low
concentrations.
Laboratory
analysis
of
methane
concentration
in
the
container
headspace
to
date
has
been
performed
on
approximately
14,000
CH­
TRU
waste
containers
representing
a
broad
spectrum
of
TRU
waste
content
codes.
In
only
two
cases
has
methane
been
detected
at
concentrations
greater
than
1,000
ppm.
Methods
currently
used
by
the
Rocky
Flats
Environmental
Technology
Site
and
proposed
for
use
for
determining
methane
concentration
in
the
headspace
have
minimum
detection
limits
that
range
from
25
to
500
ppm.
Other
instruments
(
e.
g.,
gas
chromatograph
with
flame
ionization
detector
or
with
thermal
conductivity
detector)
have
minimum
detection
limits
ranging
from
5
to
100
ppm.
All
of
these
instruments
will
provide
data
of
adequate
accuracy
and
precision
to
determine
if
the
1,250
ppm
methane
screening
limit
has
been
met.

The
1,250
ppm
methane
screening
limit
concentration
is
equivalent
to:

 
2.5%
of
the
methane
lower
explosive
limit
of
5
percent
by
volume
 
Fraction
of
the
methane
contribution
to
the
flammable
gas
G
value
for
polyethylene
(
i.
e.,
[
0.1
molecules
methane/
100
eV]
/
[
4.1
molecules
flammable
gas
/
100
eV]
or
2.4%).

If
the
methane
concentration
exceeds
the
1,250
ppm
screening
limit,
the
payload
container
is
not
eligible
for
shipment
and
cannot
be
tested
under
this
procedure
and
must
be
segregated
for
repackaging
or
other
mitigation
measures.
If
the
methane
concentration
is
less
than
or
equal
to
1,250
ppm,
and
if
flammable
VOCs
could
be
present
at
concentrations
greater
than
500
ppm
in
the
payload
container
headspace
based
on
process
knowledge,
proceed
to
Section
4.6.2.5,
Determine
Concentration
of
Flammable
VOCs
Using
PFs.
Otherwise,
mark
the
appropriate
box
in
Section
3
of
the
Data
Sheet
that
shows
that
flammable
VOCs
in
the
headspace
are
less
than
or
equal
to
500
ppm
and
proceed
to
Section
4.6.2.5,
Determine
Compliance
with
the
Packaging
Design
Pressure
Limit
by
Theoretical
Analysis.
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HANFORD
SITE
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WASTE
CERTIFICATION
PLAN
Determine
Concentration
of
Flammable
VOCs
Using
PFs
1.
Based
on
the
methodology
presented
in
Section
4.6.2.4,
determine
the
payload
container
headspace
concentration
(
90%
steady­
state)
from
the
headspace
measurement
for
each
of
the
flammable
VOCs
listed
in
Table
5.2­
2.
If
additional
flammable
VOCs
(
i.
e.,
not
listed
in
Table
4.6.2­
2)
are
identified
in
concentrations
greater
than
500
ppm
total,
the
following
process
shall
be
used
to
include
these
VOCs
in
the
analysis
for
compliance
with
flammable
(
gas/
VOC)
limits.

Each
flammable
VOC
not
listed
in
Table
4.6.2­
2
will
be
identified
by
name
and
corresponding
Chemical
Abstracts
Service
number.
A
list
of
these
VOCs
shall
be
submitted
by
the
shipper
to
the
WIPP
CH­
TRU
Payload
Engineer
for
evaluation.
For
each
VOC,
the
WIPP
CH­
TRU
Payload
Engineer
will
direct
the
evaluation
of
required
physical
and
chemical
properties
in
order
to
calculate
the
PF
using
the
methodology
documented
in
Appendix
3.9
of
the
CH­
TRU
Payload
Appendices
and
the
Group
Contribution
Factor
(
GCF)
using
the
methodology
documented
in
Appendix
3.10
of
the
CH­
TRU
Payload
Appendices.

Record
the
measured
concentration
in
units
of
ppm
for
each
flammable
VOC
and
for
the
sum
of
flammable
VOCs
(
Section
3
of
the
Data
Sheet).
If
the
sum
of
flammable
VOCs
in
the
payload
container
headspace
is
less
than
or
equal
to
500
ppm,
proceed
to
Section
4.6.2.5,
Determine
Compliance
with
the
Packaging
Design
Pressure
Limit
by
Theoretical
Analysis.
Otherwise,
proceed
to
Step
B.

2.
For
each
flammable
VOC,
multiply
the
flammable
VOC
concentration
in
the
payload
container
headspace
by
the
appropriate
PF
to
predict
the
concentration
of
each
flammable
VOC
within
the
innermost
confinement
layer.
The
PFs
are
determined
for
the
payload
container
based
on
its
packaging
as
described
in
Section
4.6.2.4.
Record
the
predicted
innermost
confinement
layer
concentration
for
each
flammable
VOC
(
Section
3
of
the
Data
Sheet).

3.
Sum
the
predicted
innermost
confinement
layer
flammable
VOC
concentrations
and
record
the
sum
(
Section
3
of
the
Data
Sheet).

4.
Proceed
to
Section
4.6.2.5,
Determine
Compliance
with
the
Packaging
Design
Pressure
Limit
by
Theoretical
Analysis
to
see
if
compliance
with
the
TRUPACTII
design
pressure
limit
can
be
established
by
theoretical
analysis.

Determine
Compliance
with
the
Packaging
Design
Pressure
Limit
by
Theoretical
Analysis
As
described
in
Section
3.4.4
of
the
TRUPACT­
II
SARs,
compliance
with
the
TRUPACT­
II
design
pressure
limits
can
be
demonstrated
by
conservative
theoretical
analysis
up
to
the
wattage
limits
shown
in
Table
4.6.2­
9
for
Waste
Types
I,
II,
and
III.
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HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
Table
4.6.2­
9
 
Wattage
Limits
for
Theoretical
Analysis
of
Design
Pressure
Limit
Waste
Type
Container
Type
Wattage
Limit
per
Payload
Container
and
per
TRUPACT­
II
55­
gallon
drum
40
Other
container
typesa
40
I
TDOP
40
55­
gallon
drum
40
Other
container
typesa
40
II
TDOP
40
55­
gallon
drum
37
Direct
load
SWB
23
55­
gallon
drum
in
an
SWB
overpack
38
85­
gallon
drum,
85­
gallon
drum
overpack,
or
55­
gallon
drum
in
an
85­
gallon
drum
overpack
26
III
TDOP
18
aOther
container
types
are
defined
as
follows:
direct
load
SWB,
55­
gallon
drum
in
an
SWB
overpack,
85­
gallon
drum,
85­
gallon
drum
overpack,
and
55­
gallon
drum
in
an
85­
gallon
drum
overpack.
NA
=
Not
applicable
For
cases
where
the
wattage
limits
specified
in
Table
4.6.2­
9
are
exceeded
but
the
packaging
design
limit
of
40
watts
per
TRUPACT­
II
is
met,
compliance
with
the
container
flammable
gas
generation
rate
limit
by
the
method
described
in
Section
4.6.2.5,
under
Determine
Compliance
with
Flammable
Gas
Generation
Rate
or
Section
4.6.2.5,
under
Determine
Compliance
with
Flammable
(
Gas/
VOC)
Concentration
limit,
can
be
used
to
evaluate
compliance
with
the
total
gas
generation
rate
limit.
Because
the
primary
mechanism
for
gas
generation
for
both
flammable
and
total
gas
for
Waste
Types
I,
II,
and
III
is
radiolysis,
compliance
with
the
flammable
gas
generation
rate
limit
implies
actual
G
values
(
both
flammable
and
total)
that
are
much
lower
than
those
used
to
derive
the
limits
in
Table
4.6.2­
9.
Therefore,
compliance
with
the
flammable
gas
generation
rate
limits
will
ensure
compliance
with
the
total
gas
generation
rate
limits
for
these
cases
(
e.
g.,
Waste
Type
III
SWBs
greater
than
23
watts
in
a
TRUPACT­
II.
An
example
calculation
is
provided
below:

Assuming
an
SWB
of
Waste
Material
Type
III.
1
with
no
layers
of
confinement
and
a
decay
heat
loading
of
30
watts,
compliance
with
the
total
gas
generation
rate
limit
is
ensured
if
compliance
with
the
flammable
gas
generation
rate
limit
can
be
demonstrated
by
measurement
or
testing.
Using
the
equations
in
Section
4.6.2.3,
the
maximum
allowed
hydrogen
gas
generation
rate
for
the
test
category
SWB
can
be
calculated
as
1.79E­
07
moles/
second.
Based
on
the
30­
watt
decay
heat
loading
of
the
SWB
and
the
requirement
for
the
SWB
hydrogen
gas
generation
to
be
less
than
or
equal
to
1.79E­
07
moles/
second,
the
actual
G
value
(
flammable
gas)
for
this
container
can
be
calculated
as
0.06.
This
compares
to
a
theoretical
G
value
(
flammable
gas)
of
1.09
used
to
derive
the
analytical
category
limits.
Because
the
mechanism
for
both
hydrogen
and
total
gas
generation
is
HNF­
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HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
radiolysis,
a
similar
ratio
exists
between
the
actual
and
theoretical
gas
generation
rates
for
hydrogen
and
total
gas.
This
means
that
if
the
SWB
passes
the
hydrogen
gas
generation
rate
limit
of
1.79E­
07
moles/
second,
the
actual
G
value
(
total
gas)
for
this
container
will
be
lower
than
the
theoretical
G
value
used
to
derive
the
limits
in
Table
4.6.2­
9
by
a
factor
of
1.09/
0.06
=
18.
Therefore,
the
actual
total
gas
generation
from
this
container
will
be
extremely
low
and
will
easily
comply
with
the
packaging
design
pressure
limits.

Determine
the
sum
of
the
measured
decay
heat
value
and
the
decay
heat
measurement
error
(
one
standard
deviation)
for
the
payload
container
from
its
data
package.
Record
the
decay
heat
plus
the
associated
error
and
the
wattage
limit
for
the
container
and
waste
type
from
Table
4.6.2­
9
(
Section
4
of
the
Data
Sheet),
and
compare
the
two
values.
(
Note
that
the
limits
specified
in
Table
4.6.2­
9
are
per
payload
container
and
per
TRUPACT­
II.)
If
the
container
decay
heat
plus
error
is
less
than
or
equal
to
the
appropriate
value
in
Table
5.2­
9
and
the
concentration
of
flammable
VOCs
in
the
payload
container
headspace
is
less
than
or
equal
to
500
ppm,
proceed
to
Section
4.6.2.5,
under
Determine
Compliance
with
Flammable
Gas
Generation
Rate.
If
the
container
decay
heat
plus
error
is
less
than
or
equal
to
the
appropriate
value
in
Table
4.6.2­
9
and
the
concentration
of
flammable
VOCs
in
the
payload
container
headspace
is
greater
than
500
ppm,
proceed
to
Section
4.6.2.5,
under
Determine
Compliance
with
Flammable
Gas
(
Gas/
VOC)
Concentration
Limit.
If
the
container
decay
heat
plus
error
is
greater
than
the
appropriate
value
in
Table
4.6.2­
9,
then
the
container
may
be
evaluated
for
compliance
for
flammable
gas
generation
rate
limits
as
described
in
Section
4.6.2.5,
under
Determine
Compliance
with
Flammable
Gas
Generation
Rate
and
Section
4.6.2.5,
under
Determine
Compliance
with
Flammable
Gas
(
Gas/
VOC)
Concentration
Limit.
If
compliance
with
the
flammable
gas
generation
rate
limits
is
demonstrated,
then
the
total
gas
generation
rate
limits
are
met
as
described
above.

Determine
Compliance
with
Flammable
Gas
Generation
Rate
Limit
1.
Calculate
the
flammable
gas
generation
rate
(
FGGR)
within
the
innermost
layer
of
confinement
using
the
measured
flammable
gas
concentration
in
the
container
and
the
time
history
of
the
payload
container
using
the
AltMeth
algorithm
described
in
Appendix
3.10
of
the
CH­
TRU
Payload
Appendices.
Headspace
measurement
methods
and
associated
QA/
QC
requirements
are
provided
in
the
QAPP.
5
Record
the
calculated
FGGR
(
Section
4
of
the
Data
Sheet).

2.
Record
the
maximum
allowable
hydrogen
gas
generation
rate
for
the
corresponding
shipping
category
determined
in
accordance
with
the
methodology
described
in
Section
4.6.2.3
(
Section
4
of
the
Data
Sheet).

3.
Compare
the
calculated
FGGR
to
the
maximum
allowable
hydrogen
gas
generation
rate.
If
the
calculated
FGGR
is
less
than
or
equal
to
the
maximum
allowable
hydrogen
gas
generation
rate,
then
the
payload
container
may
be
shipped
if
compliance
with
all
other
transportation
requirements
is
demonstrated.
If
the
calculated
FGGR
exceeds
the
maximum
allowable
hydrogen
gas
generation
rate,
the
container
may
be
reassessed
for
compliance
with
transportation
HNF­
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HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
requirements
through
the
evaluation
of
a
payload
with
different
shipping
categories
or
dunnage
containers,
as
described
in
Section
4.7.4.

If
the
calculated
FGGR
for
each
overpacked
container
is
less
than
or
equal
to
the
maximum
allowable
hydrogen
gas
generation
rate
for
the
payload
shipping
category,
then
the
overpack
may
be
shipped
if
compliance
with
all
other
transportation
requirements
is
demonstrated.

If
the
calculated
FGGR
of
any
type
of
overpacked
container
exceeds
the
maximum
allowable
hydrogen
gas
generation
rate
limit
of
the
payload
shipping
category,
the
container
may
be
reassessed
under
the
logic
of
Appendix
2.4
of
the
CH­
TRU
Payload
Appendices.

If
the
calculated
FGGR
of
an
overpacked
container
exceeds
the
maximum
allowable
hydrogen
gas
generation
rate
for
the
payload
shipping
category
and
is
not
reassessed
through
the
logic
of
Appendix
2.4
of
the
CH­
TRU
Payload
Appendices,
then
the
overpack
shall
be
reconfigured,
or
mitigative
measures
shall
be
adopted.
For
mixing
of
container
shipping
categories
within
an
overpack
configuration,
the
configuration
must
be
assessed
under
the
logic
of
Section
4.7.4
and
Appendix
2.4
of
the
CH­
TRU
Payload
Appendices.

If
the
above
relevant
limits
are
met,
the
payload
container
satisfies
the
test
criteria.
If
the
Data
Sheet
is
used
to
document
compliance,
then
the
Data
Sheet
is
signed
by
the
Transportation
Certification
Official.
If
compliance
is
determined
using
a
verified/
validated
software
package,
then
the
necessary
data
are
stored
electronically
and
the
Transportation
Certification
Official
signs
the
completed
PCTCD
or
OPCTCD,
as
appropriate.
The
payload
container
qualifies
for
shipment
after
verification
of
all
of
the
transportation
parameters.
Containers
that
do
not
meet
the
test
category
criteria
are
segregated
for
repackaging
or
reprocessing.

Determine
Compliance
with
Flammable
(
Gas/
VOC)
Concentration
Limit
1.
Calculate
the
FGGR
within
the
innermost
layer
of
confinement
using
the
measured
flammable
gas
concentration
in
the
payload
container
and
the
time
history
of
the
container
(
based
on
the
method
in
Appendix
3.10
of
the
CH­
TRU
Payload
Appendices).
Headspace
measurement
methods
and
associated
QA/
QC
requirements
are
provided
in
the
QAPP5.
Record
the
calculated
FGGR
(
Section
4
of
the
Data
Sheet).

2.
Calculate
the
concentration
of
the
flammable
gas
within
the
innermost
confinement
layer
at
the
end
of
the
shipping
period
inside
a
TRUPACT­
II
(
Xinner)
using
the
following
equation:

T
inner
R
CG
X
*
=

where,
HNF­
2600,
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HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
CG
=
Calculated
FGGR
(
mole/
second)
RT
=
The
total
resistance
to
hydrogen
release
(
second/
mole)
(
see
Appendix
2.2
of
the
CH­
TRU
Payload
Appendices).

Record
the
calculated
innermost
confinement
layer
flammable
gas
concentration
(
Section
4
of
the
Data
Sheet).

3.
Calculate
the
container­
specific
MLEL
within
the
innermost
confinement
layer
using
the
flammable
group
method
as
described
in
Appendix
3.10
of
the
CH­
TRU
Payload
Appendices
using
the
following
equation:

i
i
GCF
f
%
MLEL
 
=
100
where,

MLEL
=
Mixture
lower
explosive
limit
(
volume
percent)
fi
=
Fraction
of
flammable
gas
i
in
mixture
on
an
air­
free
and
nonflammable
VOC­
free
basis
(
i.
e.,
the
concentration
of
flammable
compound
i
divided
by
the
sum
of
the
concentrations
of
flammable
VOCs
and
flammable
gas)
GCFi
=
Group
contribution
factor
for
compound
i.

The
GCF
values
for
various
compounds
are
listed
in
Appendix
3.10
of
the
CH­
TRU
Payload
Appendices.
Record
the
MLEL
(
Section
4
of
the
Data
Sheet).

4.
Calculate
and
record
the
sum
of
the
concentrations
of
the
flammable
gas
in
the
innermost
confinement
layer
and
the
flammable
VOCs
in
the
innermost
confinement
layer
(
Section
4
of
the
Data
Sheet).

5.
Compare
the
sum
of
the
flammable
gas
and
flammable
VOC
concentrations
within
the
innermost
confinement
layer
to
the
calculated
MLEL.
If
the
sum
of
the
flammable
gas
and
VOC
concentrations
is
less
than
or
equal
to
the
MLEL,
then
the
container
may
be
shipped
if
compliance
with
all
other
transportation
requirements
is
demonstrated.

If
the
sum
of
the
flammable
gas
and
VOC
concentrations
exceeds
the
MLEL,
the
container
may
be
reassessed
for
compliance
with
transportation
requirements
through
the
evaluation
of
a
payload
with
different
shipping
categories
or
dunnage
containers.
If
the
sum
of
the
flammable
gas
and
VOC
concentrations
exceeds
the
MLEL
and
the
container
is
not
reassessed,
the
container
shall
be
reconfigured
or
mitigative
measures
shall
be
adopted.

6.
In
the
case
of
an
overpack
configuration
with
multiple
containers
(
drums
in
an
SWB
or
TDOP)
that
consist
of
one
or
more
overpacked
payload
container(
s),
the
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HANFORD
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configuration
must
be
assessed
under
Section
4.7.1
and
Appendix
2.4
of
the
CHTRU
Payload
Appendices.

If
the
above
relevant
limits
are
met,
the
payload
container
satisfies
the
test
category
criteria.
If
the
Data
Sheet
is
used
to
document
compliance,
then
the
Data
Sheet
is
signed
by
the
Transportation
Certification
Official.
If
compliance
is
determined
using
a
verified/
validated
software
package,
then
the
necessary
data
are
stored
electronically
and
the
Transportation
Certification
Official
signs
the
completed
PCTCD
or
OPCTCD,
as
appropriate.
The
payload
container
qualifies
for
shipment
after
verification
of
all
of
the
transportation
parameters.
Containers
that
do
not
meet
the
test
category
criteria
are
segregated
for
repackaging
or
reprocessing.

Procedure
for
Testing
Hanford
does
not
perform
this
testing.

Implementation
of
Unified
Flammable
Gas
Test
Procedure
Long­
Term
Objective
The
long­
term
objective
of
the
UFGTP
is
applied
to
a
population
of
containers
with
consistent
gas
generation
properties.
The
long­
term
objective
of
the
UFGTP
may
be
implemented
once
the
required
data
have
been
collected
through
measurement
for
a
subpopulation
of
these
containers.
If
a
bounding
FGGR
value
for
compliance
determination
can
be
established
and
shown
to
be
below
the
maximum
allowable
FGGR
for
the
population,
no
further
need
exists
to
test
every
container
in
the
population.
If
the
bounding
FGGR
value
exceeds
the
maximum
allowable
FGGR,
the
population
will
continue
to
be
processed
under
the
measurement
method
of
the
UFGTP.
This
method
is
consistent
with
that
used
in
the
determination
of
dose­
dependent
G
values
in
Appendix
3.3
of
the
CH­
TRU
Payload
Appendices.

Site
implementation
of
the
UFGTP
long­
term
objective
must
be
documented
in
site­
specific
programs
approved
by
DOE­
CBFO
and
Hanford
has
no
such
programs
at
this
time.

4.6.3
Venting
and
Aspiration
4.6.3.1
Requirements
Payload
containers
that
have
been
stored
in
an
unvented
condition
(
i.
e.,
no
filter
and/
or
unpunctured
liner)
shall
be
aspirated
for
the
specific
length
of
time
to
ensure
equilibration
of
any
gases
that
may
have
accumulated
in
the
closed
container.
For
payload
containers
with
waste
types
in
packaging
configurations
that
do
not
generate
any
flammable
gas,
aspiration
is
not
required
(
i.
e.,
Waste
Material
Type
II.
2).
Note:
The
aspiration
requirement
is
applicable
only
to
containers
that
have
been
stored
in
an
unvented
condition.
The
derivation
of
aspiration
times
is
outlined
in
Appendix
3.7
of
the
CH­
TRU
Payload
Appendices.
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4.6.3.2
Compliance
and
Verification
The
following
sections
describe
the
three
options
that
are
available
for
determining
the
required
aspiration
time.
Tables
in
this
section
present
aspiration
times
for
common
packaging
configurations.

Project
personnel
ensure
that
all
containers
are
properly
vented
or
repackage
CH
TRU
waste
into
vented
containers.
Unvented
containers
will
be
allowed
to
aspirate
for
a
period
of
time
determined
using
one
of
the
options
and
applicable
aspiration
tables
presented
in
this
Certification
Plan.
If
option
2
or
3
is
used
to
determine
aspiration
time,
project
personnel
follow
headspace­
gas
sampling
requirements
identified
in
TRU­
OP­
001
to
analyze
the
headspace­
gas
samples.
Analytical
personnel
determine
the
concentration
of
hydrogen
in
the
headspace­
gas
samples
in
accordance
with
LA­
523­
426.
The
WCO
determines
the
aspiration
option
used
in
accordance
with
WMP­
400,
Section
7.1.8
and
enters
the
information
required
to
compute
the
aspiration
time
in
WWIS
in
accordance
with
WMP­
400,
Section
7.1.5.

Refer
to
Appendix
A,
column
"
CH­
TRAMPAC
(&
Certification
Plan
Section,
if
applicable)"
row
5.3,
which
contains
the
titles
of
applicable
procedures
that
implement
the
requirements
of
this
subsection.

Option
1
 
Aspiration
Time
Based
on
Date
of
Payload
Container
Closure
Compliance
shall
be
by
records
and
database
information.
For
sites
using
this
option,
the
steps
outlined
below
shall
be
implemented
to
determine
the
aspiration
time
for
a
payload
container.

1.
The
potential
shipping
category
of
the
payload
container
shall
be
known.

2.
The
duration
for
which
the
container
has
been
in
a
closed
condition
should
be
computed
from
a
knowledge
of
the
date
of
closure
of
the
drum.
This
closure
time
should
be
rounded
up
to
the
next
highest
time
period
listed
in
Tables
4.6.3­
1,
4.6.3­
2,
or
4.6.3­
3.

3.
The
required
aspiration
time
corresponding
to
this
closure
time
shall
then
be
read
from
the
same
table
under
the
column
for
the
number
of
layers
of
confinement
associated
with
the
appropriate
container
shipping
category.

4.
The
container
shall
be
qualified
for
shipment
only
after
being
aspirated
for
at
least
this
period
of
time.

Option
2
 
Headspace
Gas
Sampling
at
the
Time
of
Venting
Compliance
shall
be
by
measurement
of
headspace
gas
concentrations
and
records.
For
sites
using
this
option,
the
steps
outlined
below
shall
be
implemented
to
determine
the
aspiration
time
for
a
payload
container.

1.
The
potential
shipping
category
of
the
payload
container
shall
be
known.
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HANFORD
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2.
At
the
time
of
venting,
a
headspace
sample
shall
be
taken
from
the
container
headspace
(
Option
2A)
or
from
the
rigid
liner
headspace
(
Option
2B)
and
analyzed
for
the
hydrogen
concentration.

3.
The
measured
headspace
concentration
of
all
hydrogen
shall
be
rounded
up
to
the
next
highest
mole
percentage
listed
in
Tables
4.6.3­
4,
4.6.3­
5,
4.6.3­
6,
4.6.3­
7,
4.6.3­
8,
or
4.6.3­
9
determined
by
Option
2A
or
2B,
as
appropriate.

4.
The
required
aspiration
time
corresponding
to
this
molar
percentage
shall
be
read
from
the
same
table
under
the
column
for
the
number
of
layers
of
confinement
associated
with
the
appropriate
container
shipping
category.

5.
The
container
shall
be
qualified
for
shipment
only
after
being
aspirated
for
at
least
this
period
of
time.

Option
3
 
Headspace
Gas
Sampling
During
Aspiration
Compliance
shall
be
by
direct
measurement
of
the
headspace
gas
concentration.
For
sites
using
this
option,
the
steps
outlined
below
shall
be
implemented
to
determine
the
aspiration
time
for
a
payload
container.

1.
The
potential
shipping
category
of
the
payload
container
shall
be
known.

2.
Prior
to
measuring
the
hydrogen
concentration
in
the
payload
container
headspace,
the
drum
shall
be
vented
for
at
least
two
weeks.

3.
The
measured
headspace
concentration
of
hydrogen
shall
be
rounded
up
to
the
next
highest
mole
percentage
listed
in
Tables
4.6.3­
10,
4.6.3­
11,
or
4.6.3­
12.

4.
The
required
aspiration
time
corresponding
to
this
molar
percentage
shall
be
read
from
the
same
table
under
the
column
for
the
number
of
layers
of
confinement
associated
with
the
appropriate
container
shipping
category.

5.
The
container
shall
be
qualified
for
shipment
only
after
being
aspirated
for
this
period
of
time.
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Table
4.6.3­
1
Aspiration
Times
Based
on
Date
of
Drum
Closure
(
Waste
Type
Ia)

Age
of
Waste
By
Number
of
Layers
of
Confinement
(
Days)
(
Months)
(
Years)
0
1
2
3
4
1
0.083
0
0
0
0
0
2
0.167
92
92
91
0
0
3
0.250
115
117
120
11
2
4
0.333
128
131
135
37
19
5
0.417
137
141
146
101
35
6
0.500
144
149
154
192
56
7
0.583
150
155
160
239
111
8
0.667
154
160
166
270
219
9
0.750
159
164
171
294
281
10
0.833
162
168
175
312
323
11
0.917
166
172
178
328
355
12
1.000
169
175
182
341
380
14
1.167
174
180
188
363
419
16
1.333
178
185
193
380
449
18
1.500
182
189
197
395
473
20
1.667
186
193
201
407
493
22
1.833
189
196
204
418
510
24
2.000
192
199
207
428
526
26
2.167
194
202
210
437
539
28
2.333
197
205
213
445
551
30
2.500
199
207
215
452
562
32
2.667
201
209
218
459
572
34
2.833
201
211
220
465
582
36
3.000
201
211
222
471
590
38
3.167
201
211
222
477
598
40
3.333
201
211
222
482
606
42
3.500
201
211
222
487
613
44
3.667
201
211
222
491
620
46
3.833
201
211
222
496
626
48
4.000
201
211
222
500
633
50
4.167
201
211
222
504
638
52
4.333
201
211
222
508
644
54
4.500
201
211
222
512
649
56
4.667
201
211
222
515
654
58
4.833
201
211
222
519
659
60
5.000
201
211
222
522
664
66
5.500
201
211
222
531
677
72
6.000
201
211
222
540
690
78
6.500
201
211
222
548
701
84
7.000
201
211
222
555
711
90
7.500
201
211
222
561
720
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Table
4.6.3­
1
Aspiration
Times
Based
on
Date
of
Drum
Closure
(
Waste
Type
Ia)
(
Continued)

Age
of
Waste
By
Number
of
Layers
of
Confinement
(
Days)
(
Months)
(
Years)
0
1
2
3
4
96
8.000
201
211
222
568
729
102
8.500
201
211
222
568
737
108
9.000
201
211
222
568
745
114
9.500
201
211
222
568
753
120
10.000
201
211
222
568
760
132
11.000
201
211
222
568
760
144
12.000
201
211
222
568
760
156
13.000
201
211
222
568
760
168
14.000
201
211
222
568
760
180
15.000
201
211
222
568
760
192
16.000
201
211
222
568
760
204
17.000
201
211
222
568
760
216
18.000
201
211
222
568
760
228
19.000
201
211
222
568
760
240b
20.000
201
211
222
568
760
aAspiration
times
for
Waste
Material
Types
I.
1,
I.
2,
and
I.
3
are
identical.
bFor
wastes
older
than
240
months
(
20
years),
the
aspiration
times
for
240
months
shall
be
used.
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Table4.6.3­
2
Aspiration
Times
Based
on
Date
of
Drum
Closure
(
Waste
Material
Type
II.
1)

Age
of
Waste
By
Number
of
Layers
of
Confinement
(
Days)
(
Months)
(
Years)
0
1
2
3
4
5
6
1
0.083
0
0
0
0
0
0
0
2
0.167
91
44
0
0
0
0
0
3
0.250
134
141
0
0
0
0
0
4
0.333
155
174
2
0
0
0
0
5
0.417
170
193
12
4
2
0
0
6
0.500
180
208
72
9
7
5
3
7
0.583
189
219
259
14
11
8
6
8
0.667
196
229
341
19
13
12
9
9
0.750
202
237
394
27
16
13
12
10
0.833
208
244
434
49
21
17
15
11
0.917
212
250
464
290
24
19
17
12
1.000
217
256
491
427
29
22
19
14
1.167
224
265
533
582
48
27
23
16
1.333
230
273
565
677
454
35
27
18
1.500
236
280
592
749
678
49
34
20
1.667
241
286
615
804
815
423
39
22
1.833
245
292
634
848
913
727
51
24
2.000
249
297
651
887
991
910
345
26
2.167
253
301
666
919
1055
1041
739
28
2.333
256
306
680
948
1110
1144
971
30
2.500
260
310
693
975
1157
1228
1136
32
2.667
262
313
706
997
1199
1298
1264
34
2.833
265
317
717
1021
1236
1359
1369
36
3.000
268
320
727
1041
1270
1414
1457
38
3.167
270
323
737
1059
1298
1463
1531
40
3.333
272
326
745
1074
1329
1507
1600
42
3.500
275
328
754
1091
1355
1547
1660
44
3.667
277
331
762
1107
1379
1582
1715
46
3.833
279
333
769
1122
1402
1618
1765
48
4.000
279
336
777
1135
1424
1650
1810
50
4.167
279
338
784
1147
1444
1680
1851
52
4.333
279
340
791
1159
1463
1708
1892
54
4.500
279
340
797
1171
1479
1734
1929
56
4.667
279
340
803
1182
1498
1759
1963
58
4.833
279
340
809
1192
1515
1783
1996
60
5.000
279
340
815
1203
1530
1805
2027
66
5.500
279
340
831
1232
1572
1865
2110
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Table
4.6.3­
2
Aspiration
Times
Based
on
Date
of
Drum
Closure
(
Waste
Material
Type
II.
1)
(
Continued)

Age
of
Waste
By
Number
of
Layers
of
Confinement
(
Days)
(
Months)
(
Years)
0
1
2
3
4
5
6
72
6.000
279
340
845
1258
1613
1919
2183
78
6.500
279
340
858
1282
1646
1970
2247
84
7.000
279
340
870
1303
1678
2014
2306
90
7.500
279
340
881
1323
1709
2055
2358
96
8.000
279
340
892
1341
1737
2092
2407
102
8.500
279
340
892
1359
1762
2126
2451
108
9.000
279
340
892
1375
1785
2157
2493
114
9.500
279
340
892
1390
1808
2188
2531
120
10.000
279
340
892
1404
1829
2216
2567
132
11.000
279
340
892
1430
1868
2268
2633
144
12.000
279
340
892
1430
1903
2315
2692
156
13.000
279
340
892
1430
1935
2358
2746
168
14.000
279
340
892
1430
1963
2397
2795
180
15.000
279
340
892
1430
1963
2433
2842
192
16.000
279
340
892
1430
1963
2467
2885
204
17.000
279
340
892
1430
1963
2499
2924
216
18.000
279
340
892
1430
1963
2528
2960
228
19.000
279
340
892
1430
1963
2528
2995
240a
20.000
279
340
892
1430
1963
2528
3028
aFor
wastes
older
than
240
months
(
20
years),
the
aspiration
times
for
240
months
shall
be
used.
HNF­
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152
of
281
5/
11/
2005
HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
Table
4.6.3­
3
Aspiration
Times
Based
on
Date
of
Drum
Closure
(
Waste
Type
IIIa)

Age
of
Waste
By
Number
of
Layers
of
Confinement
(
Days)
(
Months)
(
Years)
0
1
2
3
4
5
6
1
0.083
0
0
0
0
0
0
0
2
0.167
94
73
0
0
0
0
0
3
0.250
130
138
0
0
0
0
0
4
0.333
149
165
9
3
0
0
0
5
0.417
162
182
28
9
6
4
2
6
0.500
172
195
193
16
11
8
6
7
0.583
179
205
285
23
15
12
10
8
0.667
186
213
338
32
20
16
13
9
0.750
191
220
376
60
24
19
17
10
0.833
196
226
406
274
30
23
20
11
0.917
201
232
430
392
36
26
23
12
1.000
205
237
450
468
46
30
25
14
1.167
212
245
483
570
338
39
31
16
1.333
218
252
509
639
571
56
38
18
1.500
223
259
531
691
703
382
46
20
1.667
227
264
550
733
795
653
63
22
1.833
231
269
566
769
865
813
419
24
2.000
235
274
581
799
923
927
721
26
2.167
238
278
594
825
971
1016
907
28
2.333
242
281
605
849
1013
1088
1042
30
2.500
244
285
616
870
1049
1149
1147
32
2.667
247
288
626
890
1082
1202
1234
34
2.833
250
291
635
907
1111
1249
1307
36
3.000
252
294
644
924
1138
1290
1371
38
3.167
254
297
652
939
1163
1328
1427
40
3.333
256
299
660
953
1186
1362
1477
42
3.500
258
302
667
966
1207
1394
1523
44
3.667
258
304
673
979
1227
1423
1565
46
3.833
258
306
680
991
1245
1450
1603
48
4.000
258
309
686
1002
1263
1476
1638
50
4.167
258
309
692
1013
1279
1499
1672
52
4.333
258
309
698
1023
1295
1522
1702
54
4.500
258
309
703
1033
1310
1543
1732
56
4.667
258
309
708
1042
1324
1563
1759
58
4.833
258
309
713
1051
1338
1583
1785
60
5.000
258
309
718
1060
1351
1601
1810
66
5.500
258
309
731
1083
1387
1651
1877
72
6.000
258
309
743
1105
1419
1696
1936
78
6.500
258
309
755
1125
1449
1736
1989
84
7.000
258
309
765
1143
1475
1773
2036
HNF­
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REV
15
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153
of
281
5/
11/
2005
HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
Table
4.6.3­
3
Aspiration
Times
Based
on
Date
of
Drum
Closure
(
Waste
Type
IIIa)
(
Continued)

Age
of
Waste
By
Number
of
Layers
of
Confinement
(
Days)
(
Months)
(
Years)
0
1
2
3
4
5
6
90
7.500
258
309
765
1159
1500
1806
2079
96
8.000
258
309
765
1175
1523
1837
2119
102
8.500
258
309
765
1189
1544
1866
2156
108
9.000
258
309
765
1203
1564
1893
2190
114
9.500
258
309
765
1216
1583
1918
2222
120
10.000
258
309
765
1228
1600
1942
2253
132
11.000
258
309
765
1228
1633
1985
2308
144
12.000
258
309
765
1228
1662
2024
2358
156
13.000
258
309
765
1228
1689
2060
2403
168
14.000
258
309
765
1228
1689
2093
2444
180
15.000
258
309
765
1228
1689
2124
2483
192
16.000
258
309
765
1228
1689
2152
2518
204
17.000
258
309
765
1228
1689
2152
2552
216
18.000
258
309
765
1228
1689
2152
2583
228
19.000
258
309
765
1228
1689
2152
2612
240b
20.000
258
309
765
1228
1689
2152
2612
aAspiration
times
for
Waste
Material
Types
III.
1,
III.
2,
and
III.
3
are
identical.
bFor
wastes
older
than
240
months
(
20
years),
the
aspiration
times
for
240
months
shall
be
used.
HNF­
2600,
REV
15
Page
154
of
281
5/
11/
2005
HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
Table
4.6.3­
4
Aspiration
Times
Based
on
Container
Headspace
Gas
Sampling
at
Time
of
Venting
(
Waste
Type
Ia)

By
Number
of
Layers
of
Confinement
(
Days)
Mol
%
H2
in
headspace
0
1
2
3
4
0.1
33
40
45
22
23
0.2
79
86
91
65
49
0.3
94
101
107
156
90
0.4
103
109
116
207
192
0.5
109
116
123
236
254
0.6
114
121
128
257
292
0.7
117
124
132
273
320
0.8
121
128
135
285
342
0.9
123
131
138
296
359
1
126
133
141
305
374
1.1
128
135
143
313
387
1.2
130
137
145
320
398
1.3
131
139
147
326
408
1.4
133
141
149
332
417
1.5
134
142
150
337
425
1.6
136
144
152
342
432
1.7
137
145
153
347
439
1.8
138
146
154
351
445
1.9
139
147
155
355
451
2
140
148
157
358
457
2.1
141
149
158
362
462
2.2
142
150
159
365
467
2.3
143
151
160
368
472
2.4
144
152
161
371
476
2.5
145
153
162
374
480
2.6
146
154
162
377
484
2.7
146
155
163
379
488
2.8
147
155
164
382
492
2.9
148
156
165
384
495
3
149
157
166
386
499
3.1
149
158
166
389
502
3.2
150
158
167
391
505
3.3
150
159
168
393
508
3.4
151
159
168
395
511
3.5
152
160
169
397
514
3.6
152
161
169
399
517
3.7
153
161
170
400
519
3.8
153
162
171
402
522
3.9
154
162
171
404
524
4
154
163
172
405
527
4.1
155
163
172
407
529
HNF­
2600,
REV
15
Page
155
of
281
5/
11/
2005
HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
Table
4.6.3­
4
Aspiration
Times
Based
on
Container
Headspace
Gas
Sampling
at
Time
of
Venting
(
Waste
Type
Ia)
(
Continued)

By
Number
of
Layers
of
Confinement
(
Days)
Mol
%
H2
in
headspace
0
1
2
3
4
4.2
155
164
173
409
532
4.3
156
164
173
410
534
4.4
156
165
174
412
536
4.5
156
165
174
413
538
4.6
157
166
175
415
540
4.7
157
166
175
416
542
4.8
158
166
176
417
544
4.9
158
167
176
419
546
5
158
167
176
420
548
6
162
171
180
432
565
7
165
174
184
442
580
8
168
177
186
450
593
9
170
179
189
458
604
10
172
181
191
465
614
11
174
183
193
471
623
12
175
185
195
477
631
13
177
187
197
482
639
14
178
188
198
487
646
15
180
189
200
491
653
16
181
191
201
496
660
17
182
192
203
500
666
18
183
193
204
504
671
19
184
194
205
507
677
20
185
195
206
511
682
21
186
196
207
514
687
22
187
197
208
518
692
23
188
198
209
521
697
24
189
199
210
524
701
25
190
200
211
527
706
26
191
201
212
530
710
27
191
202
213
532
714
28
192
203
214
535
718
29
193
203
214
538
722
30
193
204
215
540
725
35
197
207
219
552
742
40
199
210
222
562
758
aAspiration
times
for
Waste
Material
Types
I.
1,
I.
2
and
I.
3
are
identical.
HNF­
2600,
REV
15
Page
156
of
281
5/
11/
2005
HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
Table
4.6.3­
5
Aspiration
Times
Based
on
Container
Headspace
Gas
Sampling
at
Time
of
Venting
(
Waste
Material
Type
II.
1)

By
Number
of
Layers
of
Confinement
(
Days)
Mol
%
H2
in
headspace
0
1
2
3
4
5
6
0.1
52
0
1
1
2
4
5
0.2
112
119
4
7
9
10
12
0.3
132
149
14
13
14
16
17
0.4
143
165
57
18
19
19
20
0.5
152
177
215
24
22
22
22
0.6
158
185
287
34
26
25
26
0.7
164
192
333
106
31
29
28
0.8
168
199
366
287
38
32
31
0.9
171
203
392
389
51
36
35
1
174
207
413
459
221
42
37
1.1
177
210
431
511
393
51
41
1.2
179
214
446
554
506
140
47
1.3
182
216
460
589
590
384
55
1.4
184
219
471
619
657
541
126
1.5
186
223
483
646
711
655
410
1.6
187
224
493
668
758
745
596
1.7
189
226
502
688
798
820
734
1.8
191
228
509
707
834
882
844
1.9
192
230
516
725
865
937
934
2
194
232
525
742
894
985
1011
2.1
195
235
532
756
918
1027
1078
2.2
196
237
538
769
942
1066
1137
2.3
198
237
544
782
964
1101
1189
2.4
199
240
550
794
985
1131
1237
2.5
200
240
555
806
1006
1163
1281
2.6
201
243
560
816
1023
1189
1321
2.7
202
244
565
826
1040
1215
1358
2.8
203
244
570
835
1056
1239
1392
2.9
204
245
574
844
1071
1262
1422
3
205
248
579
853
1086
1285
1454
3.1
206
249
583
861
1099
1305
1481
3.2
207
249
587
869
1112
1324
1508
3.3
208
250
590
877
1125
1342
1533
3.4
209
251
594
885
1137
1360
1558
3.5
209
252
598
892
1148
1377
1582
3.6
210
253
601
899
1159
1393
1603
3.7
211
254
604
905
1170
1407
1624
3.8
212
255
608
911
1180
1423
1644
3.9
212
256
611
917
1190
1437
1663
4
213
258
614
923
1199
1451
1682
HNF­
2600,
REV
15
Page
157
of
281
5/
11/
2005
HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
Table
4.6.3­
5
Aspiration
Times
Based
on
Container
Headspace
Gas
Sampling
at
Time
of
Venting
(
Waste
Material
Type
II.
1)
(
Continued)

By
Number
of
Layers
of
Confinement
(
Days)
Mol
%
H2
in
headspace
0
1
2
3
4
5
6
4.1
214
258
617
929
1208
1464
1700
4.2
214
258
620
934
1217
1477
1717
4.3
215
259
622
940
1226
1489
1733
4.4
216
260
625
945
1234
1501
1750
4.5
216
261
628
950
1242
1513
1766
4.6
217
261
630
955
1250
1524
1780
4.7
218
262
633
960
1258
1535
1795
4.8
218
263
635
965
1265
1546
1809
4.9
219
264
638
969
1273
1556
1823
5
219
264
640
974
1280
1566
1837
6
224
271
661
1013
1340
1655
1953
7
229
276
679
1046
1394
1727
2047
8
233
281
694
1075
1436
1788
2127
9
236
285
705
1100
1475
1838
2195
10
239
289
718
1123
1509
1887
2256
11
241
293
729
1143
1540
1929
2310
12
244
296
740
1161
1568
1967
2359
13
246
298
750
1178
1594
2002
2404
14
248
301
756
1194
1617
2035
2446
15
250
302
764
1208
1639
2065
2484
16
252
306
772
1222
1660
2094
2521
17
254
308
779
1235
1680
2120
2555
18
255
310
785
1247
1698
2145
2587
19
257
312
791
1258
1715
2169
2618
20
258
312
797
1269
1732
2192
2647
21
260
314
803
1280
1748
2214
2674
22
261
317
808
1290
1763
2234
2701
23
262
317
813
1300
1778
2254
2726
24
263
320
818
1309
1792
2273
2750
25
264
320
823
1318
1805
2291
2773
26
266
323
828
1327
1818
2309
2795
27
267
323
832
1335
1830
2326
2816
28
268
324
837
1343
1842
2342
2837
HNF­
2600,
REV
15
Page
158
of
281
5/
11/
2005
HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
Table
4.6.3­
6
Aspiration
Times
Based
on
Container
Headspace
Gas
Sampling
at
Time
of
Venting
(
Waste
Type
IIIa)

By
Number
of
Layers
of
Confinement
(
Days)
Mol
%
H2
in
headspace
0
1
2
3
4
5
6
0.1
56
23
0
4
6
8
9
0.2
107
116
12
13
15
16
17
0.3
125
141
32
21
21
21
22
0.4
135
155
169
29
26
26
26
0.5
143
164
246
41
32
30
30
0.6
149
172
291
137
39
35
34
0.7
153
178
323
284
49
40
38
0.8
157
183
346
367
99
46
42
0.9
161
187
366
425
302
56
47
1.0
164
191
382
469
422
99
54
1.1
166
194
395
504
505
333
65
1.2
169
197
407
533
568
479
161
1.3
171
200
418
558
619
583
403
1.4
173
203
427
580
662
664
561
1.5
175
205
436
599
698
729
678
1.6
176
207
444
616
730
784
771
1.7
178
209
451
632
758
831
847
1.8
180
211
458
646
784
873
912
1.9
181
213
464
659
807
909
968
2.0
182
214
470
672
828
943
1018
2.1
184
216
475
683
847
973
1062
2.2
185
217
480
693
865
1000
1102
2.3
186
219
485
703
881
1026
1139
2.4
187
220
490
713
897
1049
1172
2.5
188
221
494
721
912
1071
1203
2.6
189
223
498
730
925
1092
1232
2.7
190
224
502
738
938
1111
1259
2.8
191
225
506
745
951
1129
1284
2.9
192
226
510
752
962
1146
1307
3
193
227
513
759
793
1163
1330
3.1
194
228
516
766
984
1178
1351
3.2
194
229
520
772
994
1193
1371
3.3
195
230
523
778
1004
1207
1390
3.4
196
231
526
784
1013
1220
1409
3.5
197
232
529
790
1022
1233
1426
3.6
197
233
532
795
1031
1246
1443
3.7
198
233
534
801
1039
1258
1459
3.8
199
234
537
806
1047
1269
1474
3.9
199
235
539
811
1055
1280
1489
4
200
236
542
815
1063
1291
1503
HNF­
2600,
REV
15
Page
159
of
281
5/
11/
2005
HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
Table
4.6.3­
6
Aspiration
Times
Based
on
Container
Headspace
Gas
Sampling
at
Time
of
Venting
(
Waste
Type
IIIa)
(
Continued)

By
Number
of
Layers
of
Confinement
(
Days)
Mol
%
H2
in
headspace
0
1
2
3
4
5
6
4.1
201
237
544
820
1070
1302
1517
4.2
201
237
547
825
1077
1312
1531
4.3
202
238
549
829
1084
1321
1544
4.4
202
239
551
833
1091
1331
1556
4.5
203
239
554
837
1097
1340
1568
4.6
203
240
556
841
1103
1349
1580
4.7
204
241
558
845
1109
1358
1592
4.8
204
241
560
849
1115
1366
1603
4.9
205
242
562
853
1121
1374
1614
5
205
243
564
857
1127
1382
1624
6
210
248
581
889
1178
1453
1717
7
214
253
596
917
1219
1511
1793
8
217
257
608
940
1255
1561
1857
9
220
260
619
961
1286
1604
1913
10
223
264
629
979
1314
1642
1962
11
225
266
638
995
1339
1677
2006
12
227
269
647
1010
1362
1708
2047
13
229
272
654
1024
1383
1737
2084
14
231
274
661
1037
1403
1764
2119
15
233
276
668
1049
1421
1789
2151
16
235
278
674
1061
1438
1812
2181
17
236
280
680
1071
1454
1834
2209
18
238
282
685
1082
1470
1855
2236
19
239
283
690
1091
1484
1875
2261
20
240
285
695
1100
1498
1894
2285
21
241
286
700
1109
1511
1912
2308
22
243
288
705
1118
1524
1929
2330
23
244
289
709
1126
1536
1945
2351
24
245
291
713
1133
1548
1961
2371
25
246
292
717
1141
1559
1977
2390
26
247
293
721
1148
1570
1991
2409
27
248
294
725
1155
1580
2005
2427
28
249
296
729
1162
1591
2019
2444
29
250
297
732
1168
1600
2032
2460
30
251
298
736
1175
1610
2045
2477
35
255
303
752
1204
1653
2104
2550
40
259
307
766
1230
1692
2155
2615
aAspiration
times
for
Waste
Material
Types
III.
1,
III.
2,
and
III.
3
are
identical.
HNF­
2600,
REV
15
Page
160
of
281
5/
11/
2005
HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
Table
4.6.3­
7
Aspiration
Times
Based
on
Rigid
Liner
Headspace
Gas
Sampling
at
Time
of
Venting
(
Waste
Type
Ia)

By
Number
of
Layers
of
Confinement
(
Days)
Mol
%
H2
in
rigid
liner
0
1
2
3
4
1
0
0
0
0
6
2
0
0
0
28
40
3
0
0
0
113
141
4
21
47
62
218
291
5
63
77
88
267
360
6
81
93
103
300
406
7
92
103
113
324
439
8
101
111
121
344
467
9
107
118
128
360
489
10
113
123
133
374
508
11
117
128
138
386
525
12
121
132
142
397
540
13
125
136
146
407
554
14
128
139
149
416
566
15
131
142
153
424
577
16
134
145
155
432
588
17
136
147
158
439
597
18
139
150
161
445
606
19
141
152
163
451
615
20
143
154
165
457
623
21
145
156
167
463
630
22
147
158
169
468
637
23
149
160
171
473
644
24
150
161
173
477
651
25
152
163
175
482
657
26
153
165
176
486
663
27
155
166
178
490
668
28
156
168
179
494
674
29
158
169
181
498
679
30
159
170
182
502
684
31
160
172
183
505
689
32
161
173
185
509
693
33
162
174
186
512
698
34
164
175
187
515
702
35
165
176
188
518
706
36
166
177
189
521
711
37
167
178
191
524
715
38
168
180
192
527
718
39
169
181
193
530
722
40
170
182
194
532
726
41
171
182
195
535
729
42
171
183
196
537
733
HNF­
2600,
REV
15
Page
161
of
281
5/
11/
2005
HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
Table
4.6.3­
7
Aspiration
Times
Based
on
Rigid
Liner
Headspace
Gas
Sampling
at
Time
of
Venting
(
Waste
Type
Ia)
(
Continued)

By
Number
of
Layers
of
Confinement
(
Days)
Mol
%
H2
in
rigid
liner
0
1
2
3
4
43
172
184
197
540
736
44
173
185
198
542
739
45
174
186
199
544
743
46
175
187
199
547
746
47
176
188
200
549
749
48
176
189
201
551
752
49
177
189
202
553
755
50
178
190
203
555
758
51
179
191
204
557
761
52
179
192
204
559
763
53
180
192
205
561
766
54
181
193
206
563
769
55
181
194
207
565
771
56
182
195
207
567
774
57
183
195
208
569
776
58
183
196
209
571
779
59
184
197
209
572
781
60
185
197
210
574
784
61
185
198
211
576
786
62
186
198
211
577
788
63
186
199
212
579
790
64
187
200
213
581
793
65
188
200
213
582
795
66
188
201
214
584
797
67
189
201
215
585
799
68
189
202
215
587
801
69
190
203
216
588
803
70
190
203
216
590
805
71
191
204
217
591
807
72
191
204
217
593
809
73
192
205
218
594
811
74
192
205
218
595
813
75
193
206
219
597
815
76
193
206
220
598
817
77
194
207
220
599
819
78
194
207
221
601
820
79
195
208
221
602
822
80
195
208
222
603
824
81
196
209
222
605
826
82
196
209
223
606
827
83
197
210
223
607
829
84
197
210
224
608
831
HNF­
2600,
REV
15
Page
162
of
281
5/
11/
2005
HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
Table
4.6.3­
7
Aspiration
Times
Based
on
Rigid
Liner
Headspace
Gas
Sampling
at
Time
of
Venting
(
Waste
Type
Ia)
(
Continued)

By
Number
of
Layers
of
Confinement
(
Days)
Mol
%
H2
in
rigid
liner
0
1
2
3
4
85
198
210
224
609
832
86
198
211
224
611
834
87
198
211
225
612
836
88
199
212
225
613
837
89
199
212
226
614
839
90
200
213
226
615
840
91
200
213
227
616
842
92
200
214
227
617
843
93
201
214
228
619
845
94
201
214
228
620
846
95
202
215
228
621
848
96
202
215
229
622
849
97
202
216
229
623
851
98
203
216
230
624
852
99
203
216
230
625
853
100
203
217
230
626
855
aAspiration
times
for
Waste
Material
Types
I.
1,
I.
2,
and
I.
3
are
identical.
HNF­
2600,
REV
15
Page
163
of
281
5/
11/
2005
HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
Table
4.6.3­
8
Aspiration
Times
Based
on
Rigid
Liner
Headspace
Gas
Sampling
at
Time
of
Venting
(
Waste
Material
Type
II.
1)

By
Number
of
Layers
of
Confinement
(
Days)
Mol
%
H2
in
rigid
liner
0
1
2
3
4
5
6
1
0
0
0
0
0
3
6
2
0
0
0
6
12
16
19
3
54
44
10
19
24
28
31
4
105
123
173
121
67
64
65
5
128
154
337
499
662
829
1001
6
143
173
415
647
881
1117
1356
7
154
188
466
741
1017
1295
1573
8
163
199
505
810
1116
1423
1730
9
171
208
536
865
1194
1523
1853
10
177
216
562
910
1258
1606
1955
11
182
223
584
948
1312
1676
2041
12
187
229
604
981
1359
1737
2115
13
192
235
621
1011
1401
1791
2181
14
196
240
636
1038
1439
1840
2241
15
200
245
650
1062
1473
1883
2294
16
203
249
663
1084
1504
1924
2344
17
206
253
675
1104
1533
1961
2389
18
209
257
687
1123
1559
1995
2431
19
212
260
697
1140
1584
2027
2470
20
215
263
707
1157
1607
2057
2507
21
217
266
716
1172
1629
2085
2541
22
219
269
724
1187
1649
2111
2574
23
222
272
733
1201
1669
2137
2605
24
224
275
740
1214
1687
2160
2634
25
226
277
748
1226
1705
2183
2662
26
228
280
755
1238
1722
2205
2689
27
230
282
762
1250
1738
2226
2714
28
231
284
768
1261
1753
2245
2738
29
233
286
774
1271
1768
2265
2762
30
235
289
780
1281
1782
2283
2784
31
236
291
786
1291
1796
2301
2806
32
238
292
792
1300
1809
2318
2827
33
240
294
797
1309
1822
2334
2847
34
241
296
802
1318
1834
2350
2867
35
242
298
807
1327
1846
2365
2885
36
244
300
812
1335
1858
2380
2904
37
245
301
817
1343
1869
2395
2921
38
246
303
822
1350
1880
2409
2939
39
248
304
826
1358
1890
2422
2955
40
249
306
830
1365
1901
2436
2972
41
250
307
835
1372
1911
2448
2987
HNF­
2600,
REV
15
Page
164
of
281
5/
11/
2005
HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
Table
4.6.3­
8
Aspiration
Times
Based
on
Rigid
Liner
Headspace
Gas
Sampling
at
Time
of
Venting
(
Waste
Material
Type
II.
1)
(
Continued)

By
Number
of
Layers
of
Confinement
(
Days)
Mol
%
H2
in
rigid
liner
0
1
2
3
4
5
6
42
251
309
839
1379
1920
2461
3003
43
252
310
843
1386
1930
2473
3018
44
253
312
847
1392
1939
2485
3032
45
255
313
850
1399
1948
2497
3047
46
256
314
854
1405
1957
2508
3061
47
257
315
858
1411
1965
2519
3074
48
258
317
861
1417
1974
2530
3087
49
259
318
865
1423
1982
2541
3100
50
260
319
868
1429
1990
2551
3113
51
261
320
871
1434
1998
2561
3126
52
262
321
875
1440
2006
2571
3138
53
262
323
878
1445
2013
2581
3150
54
263
324
881
1450
2020
2590
3161
55
264
325
884
1455
2028
2600
3173
56
265
326
887
1460
2035
2609
3184
57
266
327
890
1465
2042
2618
3195
58
267
328
893
1470
2049
2627
3206
59
268
329
896
1475
2055
2635
3217
60
268
330
899
1480
2062
2644
3227
61
269
331
901
1484
2068
2652
3237
62
270
332
904
1489
2075
2660
3247
63
271
333
907
1493
2081
2669
3257
64
271
334
909
1498
2087
2676
3267
65
272
334
912
1502
2093
2684
3277
66
273
335
914
1506
2099
2692
3286
67
274
336
917
1510
2105
2700
3295
68
274
337
919
1514
2111
2707
3304
69
275
338
922
1518
2116
2714
3313
70
276
339
924
1522
2122
2722
3322
71
276
340
926
1526
2128
2729
3331
72
277
340
929
1530
2133
2736
3340
73
278
341
931
1534
2138
2743
3348
74
278
342
933
1538
2144
2749
3356
75
279
343
935
1541
2149
2756
3365
76
280
344
937
1545
2154
2763
3373
77
280
344
939
1549
2159
2769
3381
78
281
345
942
1552
2164
2776
3389
79
281
346
944
1556
2169
2782
3396
80
282
346
946
1559
2174
2788
3404
81
283
347
948
1563
2179
2794
3412
82
283
348
950
1566
2183
2801
3419
HNF­
2600,
REV
15
Page
165
of
281
5/
11/
2005
HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
Table
4.6.3­
8
Aspiration
Times
Based
on
Rigid
Liner
Headspace
Gas
Sampling
at
Time
of
Venting
(
Waste
Material
Type
II.
1)
(
Continued)

By
Number
of
Layers
of
Confinement
(
Days)
Mol
%
H2
in
rigid
liner
0
1
2
3
4
5
6
83
284
349
952
1569
2188
2807
3427
84
284
349
954
1572
2193
2813
3434
85
285
350
956
1576
2197
2818
3441
86
285
351
957
1579
2202
2824
3448
87
286
351
959
1582
2206
2830
3455
88
286
352
961
1585
2210
2836
3462
89
287
353
963
1588
2215
2841
3469
90
287
353
965
1591
2219
2847
3476
91
288
354
967
1594
2223
2852
3483
92
288
354
968
1597
2228
2858
3489
93
289
355
970
1600
2232
2863
3496
94
289
356
972
1603
2236
2868
3502
95
290
356
974
1606
2240
2874
3509
96
290
357
975
1609
2244
2879
3515
97
291
358
977
1612
2248
2884
3521
98
291
358
979
1614
2252
2889
3528
99
292
359
980
1617
2256
2894
3534
100
292
359
982
1620
2260
2899
3540
HNF­
2600,
REV
15
Page
166
of
281
5/
11/
2005
HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
Table
4.6.3­
9
Aspiration
Times
Based
on
Rigid
Liner
Headspace
Gas
Sampling
at
Time
of
Venting
(
Waste
Type
IIIa)

By
Number
of
Layers
of
Confinement
(
Days)
Mol
%
H2
in
rigid
liner
0
1
2
3
4
5
6
1
0
0
0
0
2
6
10
2
0
0
2
11
17
21
25
3
46
46
19
27
33
37
40
4
96
113
196
231
259
296
343
5
118
140
310
468
626
788
953
6
132
158
371
580
791
1004
1218
7
143
171
413
655
898
1143
1389
8
151
181
445
711
978
1246
1515
9
158
189
470
755
1041
1328
1615
10
164
196
492
793
1094
1396
1698
11
169
203
510
824
1139
1454
1769
12
174
208
527
852
1179
1505
1831
13
178
213
541
877
1213
1550
1886
14
181
218
554
899
1245
1590
1936
15
185
222
566
920
1273
1627
1981
16
188
226
577
938
1299
1661
2022
17
191
229
588
955
1324
1692
2060
18
194
233
597
971
1346
1720
2095
19
196
236
606
986
1367
1747
2128
20
199
239
614
1000
1386
1773
2159
21
201
242
622
1013
1405
1796
2188
22
203
244
629
1025
1422
1819
2216
23
205
247
636
1037
1439
1840
2242
24
207
249
643
1048
1454
1860
2266
25
209
251
649
1059
1469
1879
2290
26
211
254
655
1069
1484
1898
2313
27
213
256
661
1079
1497
1915
2334
28
215
258
667
1088
1510
1932
2355
29
216
260
672
1097
1523
1948
2375
30
218
262
677
1106
1535
1964
2394
31
219
263
682
1114
1546
1979
2412
32
221
265
687
1122
1558
1993
2430
33
222
267
692
1130
1568
2007
2447
34
224
268
696
1137
1579
2021
2463
35
225
270
700
1144
1589
2034
2479
36
226
272
704
1151
1599
2046
2495
37
227
273
709
1158
1608
2059
2510
38
229
275
712
1164
1618
2071
2525
39
230
276
716
1171
1627
2082
2539
40
231
277
720
1177
1635
2093
2552
41
232
279
724
1183
1644
2104
2566
HNF­
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281
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2005
HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
Table
4.6.3­
9
Aspiration
Times
Based
on
Rigid
Liner
Headspace
Gas
Sampling
at
Time
of
Venting
(
Waste
Type
IIIa)
(
Continued)

By
Number
of
Layers
of
Confinement
(
Days)
Mol
%
H2
in
rigid
liner
0
1
2
3
4
5
6
42
233
280
727
1189
1652
2115
2579
43
234
281
731
1195
1660
2125
2592
44
235
282
734
1200
1668
2136
2604
45
236
284
737
1206
1676
2145
2616
46
237
285
740
1211
1683
2155
2628
47
238
286
743
1216
1690
2165
2640
48
239
287
746
1221
1698
2174
2651
49
240
288
749
1226
1705
2183
2662
50
241
289
752
1231
1711
2192
2673
51
242
290
755
1236
1718
2200
2683
52
243
291
758
1241
1725
2209
2694
53
244
292
761
1245
1731
2217
2704
54
244
293
763
1250
1737
2225
2714
55
245
294
766
1254
1744
2233
2724
56
246
295
769
1258
1750
2241
2733
57
247
296
771
1263
1755
2249
2743
58
248
297
774
1267
1761
2256
2752
59
248
298
776
1271
1767
2263
2761
60
249
299
778
1275
1773
2271
2770
61
250
300
781
1279
1778
2278
2778
62
251
301
783
1283
1784
2285
2787
63
251
302
785
1286
1789
2292
2796
64
252
302
788
1290
1794
2298
2804
65
253
303
790
1294
1799
2305
2812
66
253
304
792
1297
1804
2312
2820
67
254
305
794
1301
1809
2318
2828
68
255
306
796
1304
1814
2324
2836
69
255
306
798
1308
1819
2331
2843
70
256
307
800
1311
1824
2337
2851
71
257
308
802
1315
1829
2343
2858
72
257
309
804
1318
1833
2349
2866
73
258
309
806
1321
1838
2355
2873
74
258
310
808
1324
1842
2361
2880
75
259
311
810
1327
1847
2366
2887
76
260
311
812
1331
1851
2372
2894
77
260
312
814
1334
1855
2378
2901
78
261
313
815
1337
1860
2383
2907
79
261
314
817
1340
1864
2388
2914
80
262
314
819
1343
1868
2394
2921
81
262
315
821
1346
1872
2399
2927
82
263
315
822
1348
1876
2404
2934
HNF­
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168
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281
5/
11/
2005
HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
Table
4.6.3­
9
Aspiration
Times
Based
on
Rigid
Liner
Headspace
Gas
Sampling
at
Time
of
Venting
(
Waste
Type
IIIa)
(
Continued)

By
Number
of
Layers
of
Confinement
(
Days)
Mol
%
H2
in
rigid
liner
0
1
2
3
4
5
6
83
263
316
824
1351
1880
2409
2940
84
264
317
826
1354
1884
2414
2946
85
264
317
828
1357
1888
2420
2952
86
265
318
829
1360
1892
2424
2958
87
265
319
831
1362
1896
2429
2964
88
266
319
832
1365
1899
2434
2970
89
266
320
834
1368
1903
2439
2976
90
267
320
835
1370
1907
2444
2982
91
267
321
837
1373
1910
2448
2988
92
268
321
839
1375
1914
2453
2993
93
268
322
840
1378
1918
2458
2999
94
269
323
842
1380
1921
2462
3004
95
269
323
843
1383
1925
2467
3010
96
270
324
844
1385
1928
2471
3015
97
270
324
846
1388
1931
2475
3021
98
271
325
847
1390
1935
2480
3026
99
271
325
849
1392
1938
2484
3031
100
272
326
850
1395
1941
2488
3036
aAspiration
times
for
Waste
Material
Types
III.
1,
III.
2,
and
III.
3
are
identical.
HNF­
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281
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HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
Table
4.6.3­
10
Aspiration
Times
(
in
Days)
Based
on
Headspace
Gas
Sampling
During
Aspiration
(
Waste
Type
Ia)

mol
%
0b
mol
%
1b
mol
%
2b
mol
%
3b
mol
%
4b
0.100
0
0.100
0
0.100
0
0.100
0
0.100
0
0.200
0
0.200
0
0.200
0
0.200
0
0.200
0
0.300
0
0.300
0
0.300
0
0.300
0
0.300
0
0.400
0
0.400
0
0.400
0
0.400
0
0.432
0
0.500
0
0.500
0
0.500
0
0.591
0
0.500
6
0.600
0
0.600
0
0.600
0
0.600
1
0.600
13
0.700
0
0.700
0
0.700
0
0.700
8
0.700
19
0.800
0
0.800
0
0.800
0
0.800
15
0.800
26
0.900
0
0.900
0
0.900
0
0.900
21
0.900
32
1.000
0
1.000
0
1.000
0
1.000
28
1.000
38
1.100
0
1.100
0
1.100
0
1.100
36
1.100
45
1.200
0
1.200
0
1.200
0
1.200
45
1.200
53
1.300
0
1.300
0
1.300
0
1.300
56
1.300
64
1.400
0
1.400
0
1.400
0
1.400
74
1.400
78
1.500
0
1.500
0
1.500
0
1.500
100
1.500
104
1.600
0
1.600
0
1.600
0
1.600
130
1.600
146
1.700
0
1.700
0
1.700
0
1.700
155
1.700
185
1.800
0
1.800
0
1.800
0
1.800
175
1.800
215
1.900
0
1.900
0
1.900
0
1.900
191
1.900
240
2.000
0
2.000
0
2.024
0
2.000
205
2.000
261
2.100
0
2.100
0
2.100
36
2.100
218
2.100
278
2.200
0
2.282
0
2.200
50
2.200
228
2.200
294
2.300
0
2.300
16
2.300
60
2.300
238
2.300
308
2.400
0
2.400
34
2.400
68
2.400
246
2.400
320
2.500
0
2.500
45
2.500
74
2.500
254
2.500
331
2.616
0
2.600
54
2.600
79
2.600
261
2.600
342
2.700
17
2.700
60
2.700
83
2.700
268
2.700
351
2.800
30
2.800
66
2.800
87
2.800
274
2.800
360
2.900
39
2.900
71
2.900
91
2.900
280
2.900
368
3.000
46
3.000
75
3.000
94
3.000
286
3.000
376
3.100
51
3.100
78
3.100
97
3.100
291
3.100
383
3.200
56
3.200
81
3.200
100
3.200
296
3.200
390
3.300
60
3.300
84
3.300
102
3.300
300
3.300
396
3.400
64
3.400
87
3.400
104
3.400
305
3.400
402
3.500
67
3.500
90
3.500
106
3.500
309
3.500
408
3.600
70
3.600
92
3.600
108
3.600
313
3.600
414
3.700
73
3.700
94
3.700
110
3.700
316
3.700
419
3.800
75
3.800
96
3.800
112
3.800
320
3.800
424
3.900
78
3.900
98
3.900
114
3.900
323
3.900
429
4.000
80
4.000
100
4.000
115
4.000
327
4.000
434
4.100
82
4.100
101
4.100
117
4.100
330
4.100
438
4.200
84
4.200
103
4.200
118
4.200
333
4.200
442
4.300
85
4.300
105
4.300
120
4.300
336
4.300
446
HNF­
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170
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HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
Table
4.6.3­
10
Aspiration
Times
(
in
Days)
Based
on
Headspace
Gas
Sampling
During
Aspiration
(
Waste
Type
Ia)
(
Continued)

mol
%
0b
mol
%
1b
mol
%
2b
mol
%
3b
mol
%
4b
4.400
87
4.400
106
4.400
121
4.400
339
4.400
450
4.500
89
4.500
107
4.500
122
4.500
342
4.500
454
4.600
90
4.600
109
4.600
124
4.600
344
4.600
458
4.700
92
4.700
110
4.700
125
4.700
347
4.700
462
4.800
93
4.800
111
4.800
126
4.800
350
4.800
465
4.900
94
4.900
112
4.900
127
4.900
352
4.900
469
5.000
96
5.000
114
5.000
128
5.000
354
5.000
472
6.000
106
6.000
123
6.000
137
6.000
375
6.000
500
7.000
114
7.000
131
7.000
145
7.000
392
7.000
523
8.000
120
8.000
137
8.000
151
8.000
405
8.000
542
9.000
126
9.000
142
9.000
156
9.000
417
9.000
558
10.000
130
10.000
146
10.000
160
10.000
427
10.000
572
11.000
134
11.000
150
11.000
164
11.000
436
11.000
585
12.000
137
12.000
154
12.000
167
12.000
444
12.000
596
13.000
141
13.000
157
13.000
170
13.000
452
13.000
606
14.000
143
14.000
160
14.000
173
14.000
458
14.000
616
15.000
146
15.000
162
15.000
176
15.000
465
15.000
624
16.000
148
16.000
165
16.000
178
16.000
470
16.000
632
17.000
151
17.000
167
17.000
180
17.000
476
17.000
640
18.000
153
18.000
169
18.000
182
18.000
481
18.000
647
19.000
155
19.000
171
19.000
184
19.000
486
19.000
654
20.000
157
20.000
173
20.000
186
20.000
490
20.000
660
21.000
158
21.000
174
21.000
188
21.000
495
21.000
666
22.000
160
22.000
176
22.000
189
22.000
499
22.000
672
23.000
162
23.000
178
23.000
191
23.000
503
23.000
678
24.000
163
24.000
179
24.000
192
24.000
506
24.000
683
25.000
164
25.000
181
25.000
194
25.000
510
25.000
688
26.000
166
26.000
182
26.000
195
26.000
513
26.000
693
27.000
167
27.000
183
27.000
197
27.000
517
27.000
698
28.000
168
28.000
185
28.000
198
28.000
520
28.000
702
29.000
170
29.000
186
29.000
199
29.000
523
29.000
707
30.000
171
30.000
187
30.000
200
30.000
526
30.000
711
35.000
176
35.000
192
35.000
205
35.000
540
35.000
730
40.000
181
40.000
197
40.000
210
40.000
551
40.000
747
45.000
184
45.000
200
45.000
213
45.000
562
45.000
762
50.000
188
50.000
204
50.000
217
50.000
571
50.000
776
55.000
191
55.000
207
55.000
220
55.000
580
55.000
788
60.000
194
60.000
210
60.000
223
60.000
588
60.000
799
65.000
197
65.000
212
65.000
225
65.000
595
65.000
809
70.000
199
70.000
215
70.000
228
70.000
602
70.000
819
aAspiration
times
for
Waste
Material
Types
I.
1,
I.
2,
and
I.
3
are
identical.
bNumbers
represent
the
number
of
layers
of
confinement.
HNF­
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HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
Table
4.6.3­
11
Aspiration
Times
(
in
Days)
Based
on
Headspace
Gas
Sampling
During
Aspiration
(
Waste
Material
Type
II.
1)

mol
%
0a
mol
%
1a
mol
%
2a
mol
%
3a
mol
%
4a
mol
%
5a
mol
%
6a
0.100
0
0.100
0
0.100
0
0.100
0
0.100
0
0.100
0
0.100
0
0.200
0
0.200
0
0.200
0
0.200
0
0.200
0
0.200
0
0.265
0
0.300
0
0.300
0
0.300
0
0.300
0
0.300
0
0.320
0
0.300
2
0.400
0
0.400
0
0.400
0
0.400
0
0.403
0
0.400
4
0.400
6
0.500
0
0.500
0
0.500
0
0.546
0
0.500
4
0.500
8
0.500
10
0.600
0
0.600
0
0.600
0
0.600
2
0.600
8
0.600
11
0.600
13
0.700
0
0.700
0
0.700
0
0.700
5
0.700
9
0.700
12
0.700
16
0.800
0
0.800
0
0.846
0
0.800
7
0.800
13
0.800
16
0.800
18
0.900
0
0.900
0
0.900
2
0.900
10
0.900
14
0.900
18
0.900
20
1.000
0
1.000
0
1.000
5
1.000
13
1.000
16
1.000
20
1.000
21
1.100
0
1.100
0
1.100
9
1.100
15
1.100
20
1.100
22
1.100
24
1.200
0
1.200
0
1.200
13
1.200
18
1.200
21
1.200
23
1.200
26
1.300
0
1.300
0
1.300
19
1.300
22
1.300
24
1.300
26
1.300
27
1.400
0
1.400
0
1.400
31
1.400
25
1.400
26
1.400
28
1.400
31
1.500
0
1.500
0
1.500
109
1.500
30
1.500
30
1.500
31
1.500
33
1.600
0
1.600
0
1.600
183
1.600
38
1.600
33
1.600
33
1.600
35
1.700
0
1.700
0
1.700
232
1.700
71
1.700
39
1.700
37
1.700
37
1.800
0
1.874
0
1.800
269
1.800
212
1.800
47
1.800
42
1.800
40
1.900
0
1.900
30
1.900
299
1.900
304
1.900
97
1.900
47
1.900
44
2.000
0
2.000
62
2.000
323
2.000
371
2.000
275
2.000
59
2.000
49
2.192
0
2.100
82
2.100
344
2.100
424
2.100
395
2.100
200
2.100
57
2.200
4
2.200
96
2.200
362
2.200
467
2.200
483
2.200
385
2.200
122
2.300
33
2.300
107
2.300
378
2.300
503
2.300
554
2.300
517
2.300
374
2.400
49
2.400
116
2.400
393
2.400
535
2.400
612
2.400
619
2.400
547
2.500
61
2.500
124
2.500
406
2.500
563
2.500
662
2.500
701
2.500
680
2.600
71
2.600
131
2.600
417
2.600
588
2.600
706
2.600
771
2.600
786
2.700
78
2.700
137
2.700
430
2.700
611
2.700
744
2.700
831
2.700
875
2.800
85
2.800
142
2.800
439
2.800
631
2.800
778
2.800
884
2.800
952
2.900
90
2.900
147
2.900
448
2.900
648
2.900
810
2.900
931
2.900
1019
3.000
95
3.000
151
3.000
457
3.000
667
3.000
838
3.000
971
3.000
1078
3.100
100
3.100
155
3.100
465
3.100
684
3.100
864
3.100
1010
3.100
1132
3.200
104
3.200
159
3.200
473
3.200
700
3.200
890
3.200
1047
3.200
1180
3.300
108
3.300
163
3.300
480
3.300
715
3.300
910
3.300
1080
3.300
1225
3.400
111
3.400
166
3.400
487
3.400
726
3.400
930
3.400
1110
3.400
1267
3.500
114
3.500
169
3.500
494
3.500
739
3.500
950
3.500
1139
3.500
1303
3.600
117
3.600
172
3.600
501
3.600
751
3.600
968
3.600
1163
3.600
1340
3.700
120
3.700
175
3.700
506
3.700
762
3.700
986
3.700
1188
3.700
1373
3.800
123
3.800
178
3.800
511
3.800
773
3.800
1003
3.800
1213
3.800
1404
3.900
125
3.900
180
3.900
516
3.900
783
3.900
1019
3.900
1236
3.900
1431
4.000
127
4.000
183
4.000
523
4.000
793
4.000
1035
4.000
1257
4.000
1459
4.100
130
4.100
185
4.100
528
4.100
802
4.100
1049
4.100
1278
4.100
1486
4.200
132
4.200
187
4.200
532
4.200
811
4.200
1063
4.200
1298
4.200
1512
HNF­
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172
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281
5/
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2005
HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
Table
4.6.3­
11
Aspiration
Times
(
in
Days)
Based
on
Headspace
Gas
Sampling
During
Aspiration
(
Waste
Material
Type
II.
1)
(
Continued)

mol
%
0a
mol
%
1a
mol
%
2a
mol
%
3a
mol
%
4a
mol
%
5a
mol
%
6a
4.300
134
4.300
189
4.300
537
4.300
822
4.300
1077
4.300
1316
4.300
1536
4.400
136
4.400
191
4.400
542
4.400
830
4.400
1090
4.400
1334
4.400
1559
4.500
137
4.500
193
4.500
546
4.500
838
4.500
1102
4.500
1351
4.500
1582
4.600
139
4.600
195
4.600
550
4.600
845
4.600
1114
4.600
1367
4.600
1603
4.700
141
4.700
197
4.700
554
4.700
852
4.700
1125
4.700
1380
4.700
1624
4.800
142
4.800
199
4.800
558
4.800
859
4.800
1136
4.800
1395
4.800
1643
4.900
144
4.900
200
4.900
562
4.900
865
4.900
1147
4.900
1412
4.900
1662
5.000
145
5.000
202
5.000
566
5.000
872
5.000
1157
5.000
1426
5.000
1680
6.000
158
6.000
216
6.000
598
6.000
930
6.000
1242
6.000
1540
6.000
1830
7.000
168
7.000
226
7.000
623
7.000
975
7.000
1307
7.000
1633
7.000
1947
8.000
176
8.000
237
8.000
644
8.000
1010
8.000
1365
8.000
1708
8.000
2042
9.000
182
9.000
243
9.000
662
9.000
1043
9.000
1411
9.000
1771
9.000
2122
10.000
188
10.000
250
10.000
678
10.000
1073
10.000
1452
10.000
1826
10.000
2192
11.000
193
11.000
256
11.000
692
11.000
1096
11.000
1488
11.000
1875
11.000
2254
12.000
197
12.000
261
12.000
706
12.000
1119
12.000
1521
12.000
1918
12.000
2309
13.000
202
13.000
267
13.000
716
13.000
1139
13.000
1549
13.000
1956
13.000
2359
14.000
205
14.000
271
14.000
726
14.000
1157
14.000
1577
14.000
1995
14.000
2404
15.000
209
15.000
276
15.000
736
15.000
1174
15.000
1604
15.000
2028
15.000
2448
16.000
212
16.000
280
16.000
745
16.000
1190
16.000
1626
16.000
2059
16.000
2487
17.000
215
17.000
284
17.000
753
17.000
1205
17.000
1648
17.000
2088
17.000
2524
18.000
218
18.000
287
18.000
761
18.000
1219
18.000
1668
18.000
2116
18.000
2558
19.000
221
19.000
290
19.000
768
19.000
1232
19.000
1687
19.000
2142
19.000
2591
20.000
224
20.000
293
20.000
775
20.000
1244
20.000
1706
20.000
2166
20.000
2622
21.000
226
21.000
296
21.000
782
21.000
1256
21.000
1723
21.000
2189
21.000
2651
22.000
229
22.000
299
22.000
788
22.000
1267
22.000
1740
22.000
2211
22.000
2679
23.000
231
23.000
300
23.000
794
23.000
1278
23.000
1756
23.000
2233
23.000
2705
24.000
233
24.000
302
24.000
800
24.000
1288
24.000
1771
24.000
2253
24.000
2731
25.000
235
25.000
306
25.000
806
25.000
1298
25.000
1785
25.000
2272
25.000
2755
26.000
237
26.000
308
26.000
811
26.000
1308
26.000
1799
26.000
2291
26.000
2778
27.000
239
27.000
309
27.000
816
27.000
1317
27.000
1813
27.000
2309
27.000
2801
28.000
241
28.000
312
28.000
821
28.000
1325
28.000
1825
28.000
2326
28.000
2822
29.000
242
29.000
312
29.000
826
29.000
1334
29.000
1838
29.000
2342
29.000
2843
30.000
244
30.000
314
30.000
831
30.000
1342
30.000
1850
30.000
2359
30.000
2863
35.000
250
35.000
324
35.000
852
35.000
1380
35.000
1904
35.000
2431
35.000
2953
40.000
256
40.000
330
40.000
870
40.000
1412
40.000
1953
40.000
2495
40.000
3033
45.000
263
45.000
335
45.000
886
45.000
1441
45.000
1995
45.000
2550
45.000
3102
50.000
266
50.000
339
50.000
901
50.000
1467
50.000
2033
50.000
2600
50.000
3164
55.000
271
55.000
343
55.000
914
55.000
1491
55.000
2067
55.000
2645
55.000
3219
60.000
275
60.000
346
60.000
927
60.000
1513
60.000
2098
60.000
2686
60.000
3270
65.000
278
65.000
351
65.000
938
65.000
1533
65.000
2127
65.000
2724
65.000
3317
70.000
281
70.000
354
70.000
948
70.000
1551
70.000
2154
70.000
2759
70.000
3360
aNumbers
represent
the
number
of
layers
of
confinement.
HNF­
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15
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HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
Table
4.6.3­
12
 
Aspiration
Times
(
in
Days)
Based
on
Headspace
Gas
Sampling
During
Aspiration
(
Waste
Type
IIIa)

mol
%
0b
mol
%
1b
mol
%
2b
mol
%
3b
mol
%
4b
mol
%
5b
mol
%
6b
0.100
0
0.100
0
0.100
0
0.100
0
0.100
0
0.100
0
0.100
0
0.200
0
0.200
0
0.200
0
0.200
0
0.200
0
0.200
0
0.265
0
0.300
0
0.300
0
0.300
0
0.300
0
0.300
0
0.320
0
0.300
3
0.400
0
0.400
0
0.400
0
0.400
0
0.403
0
0.400
4
0.400
7
0.500
0
0.500
0
0.500
0
0.546
0
0.500
4
0.500
8
0.500
11
0.600
0
0.600
0
0.600
0
0.600
2
0.600
8
0.600
11
0.600
14
0.700
0
0.700
0
0.700
0
0.700
5
0.700
11
0.700
14
0.700
17
0.800
0
0.800
0
0.846
0
0.800
8
0.800
13
0.800
17
0.800
20
0.900
0
0.900
0
0.900
2
0.900
11
0.900
16
0.900
20
0.900
22
1.000
0
1.000
0
1.000
5
1.000
14
1.000
19
1.000
22
1.000
25
1.100
0
1.100
0
1.100
8
1.100
17
1.100
21
1.100
25
1.100
27
1.200
0
1.200
0
1.200
12
1.200
20
1.200
24
1.200
27
1.200
29
1.300
0
1.300
0
1.300
16
1.300
23
1.300
27
1.300
30
1.300
32
1.400
0
1.400
0
1.400
21
1.400
26
1.400
30
1.400
32
1.400
34
1.500
0
1.500
0
1.500
29
1.500
30
1.500
33
1.500
35
1.500
37
1.600
0
1.600
0
1.600
53
1.600
36
1.600
37
1.600
38
1.600
40
1.700
0
1.700
0
1.700
124
1.700
44
1.700
41
1.700
42
1.700
43
1.800
0
1.874
0
1.800
174
1.800
65
1.800
48
1.800
46
1.800
46
1.900
0
1.900
29
1.900
210
1.900
166
1.900
59
1.900
52
1.900
50
2.000
0
2.000
57
2.000
238
2.000
248
2.000
132
2.000
61
2.000
56
2.192
0
2.100
75
2.100
261
2.100
307
2.100
266
2.100
103
2.100
66
2.200
5
2.200
88
2.200
280
2.200
353
2.200
359
2.200
282
2.200
107
2.300
30
2.300
98
2.300
297
2.300
391
2.300
430
2.300
408
2.300
319
2.400
46
2.400
106
2.400
312
2.400
423
2.400
487
2.400
503
2.400
470
2.500
57
2.500
113
2.500
325
2.500
451
2.500
535
2.500
579
2.500
585
2.600
66
2.600
119
2.600
337
2.600
475
2.600
577
2.600
643
2.600
677
2.700
73
2.700
124
2.700
348
2.700
497
2.700
613
2.700
697
2.700
754
2.800
79
2.800
129
2.800
358
2.800
517
2.800
645
2.800
745
2.800
821
2.900
84
2.900
133
2.900
367
2.900
535
2.900
674
2.900
787
2.900
878
3.000
89
3.000
137
3.000
376
3.000
552
3.000
700
3.000
825
3.000
930
3.100
93
3.100
141
3.100
384
3.100
567
3.100
724
3.100
859
3.100
976
3.200
97
3.200
145
3.200
391
3.200
581
3.200
746
3.200
890
3.200
1018
3.300
100
3.300
148
3.300
398
3.300
594
3.300
767
3.300
919
3.300
1056
3.400
103
3.400
151
3.400
405
3.400
607
3.400
786
3.400
946
3.400
1092
3.500
106
3.500
154
3.500
411
3.500
618
3.500
804
3.500
971
3.500
1124
3.600
109
3.600
156
3.600
417
3.600
629
3.600
820
3.600
995
3.600
1155
3.700
112
3.700
159
3.700
423
3.700
640
3.700
836
3.700
1017
3.700
1184
3.800
114
3.800
161
3.800
428
3.800
650
3.800
851
3.800
1037
3.800
1210
3.900
116
3.900
163
3.900
434
3.900
659
3.900
865
3.900
1057
3.900
1236
4.000
118
4.000
166
4.000
439
4.000
668
4.000
879
4.000
1075
4.000
1260
4.100
121
4.100
168
4.100
443
4.100
677
4.100
892
4.100
1093
4.100
1282
4.200
122
4.200
170
4.200
448
4.200
685
4.200
904
4.200
1110
4.200
1304
HNF­
2600,
REV
15
Page
174
of
281
5/
11/
2005
HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
Table
4.6.3­
12
Aspiration
Times
(
in
Days)
Based
on
Headspace
Gas
Sampling
During
Aspiration
(
Waste
Type
IIIa)
(
Continued)

mol
%
0b
mol
%
1b
mol
%
2b
mol
%
3b
mol
%
4b
mol
%
5b
mol
%
6b
4.300
124
4.300
172
4.300
452
4.300
693
4.300
916
4.300
1126
4.300
1325
4.400
126
4.400
173
4.400
456
4.400
701
4.400
927
4.400
1141
4.400
1344
4.500
128
4.500
175
4.500
461
4.500
708
4.500
938
4.500
1156
4.500
1363
4.600
129
4.600
177
4.600
464
4.600
715
4.600
948
4.600
1170
4.600
1381
4.700
131
4.700
179
4.700
468
4.700
722
4.700
958
4.700
1183
4.700
1398
4.800
132
4.800
180
4.800
472
4.800
728
4.800
968
4.800
1197
4.800
1415
4.900
134
4.900
182
4.900
476
4.900
734
4.900
977
4.900
1209
4.900
1431
5.000
135
5.000
183
5.000
479
5.000
741
5.000
986
5.000
1221
5.000
1447
6.000
147
6.000
196
6.000
509
6.000
793
6.000
1063
6.000
1324
6.000
1577
7.000
156
7.000
206
7.000
532
7.000
833
7.000
1122
7.000
1404
7.000
1677
8.000
164
8.000
214
8.000
551
8.000
867
8.000
1171
8.000
1468
8.000
1759
9.000
170
9.000
221
9.000
568
9.000
895
9.000
1212
9.000
1523
9.000
1828
10.000
175
10.000
227
10.000
582
10.000
920
10.000
1247
10.000
1570
10.000
1887
11.000
180
11.000
233
11.000
595
11.000
941
11.000
1279
11.000
1612
11.000
1940
12.000
185
12.000
238
12.000
606
12.000
961
12.000
1307
12.000
1650
12.000
1987
13.000
188
13.000
242
13.000
616
13.000
978
13.000
1333
13.000
1684
13.000
2030
14.000
192
14.000
246
14.000
626
14.000
995
14.000
1356
14.000
1715
14.000
2070
15.000
195
15.000
250
15.000
634
15.000
1010
15.000
1378
15.000
1744
15.000
2106
16.000
198
16.000
253
16.000
642
16.000
1023
16.000
1398
16.000
1771
16.000
2139
17.000
201
17.000
256
17.000
650
17.000
1036
17.000
1417
17.000
1796
17.000
2171
18.000
204
18.000
259
18.000
657
18.000
1048
18.000
1435
18.000
1820
18.000
2200
19.000
206
19.000
262
19.000
663
19.000
1060
19.000
1451
19.000
1842
19.000
2228
20.000
208
20.000
264
20.000
669
20.000
1071
20.000
1467
20.000
1863
20.000
2254
21.000
210
21.000
267
21.000
675
21.000
1081
21.000
1482
21.000
1883
21.000
2279
22.000
213
22.000
269
22.000
681
22.000
1091
22.000
1496
22.000
1902
22.000
2303
23.000
215
23.000
271
23.000
686
23.000
1100
23.000
1510
23.000
1920
23.000
2326
24.000
216
24.000
273
24.000
691
24.000
1109
24.000
1523
24.000
1937
24.000
2347
25.000
218
25.000
275
25.000
696
25.000
1118
25.000
1535
25.000
1953
25.000
2368
26.000
220
26.000
277
26.000
701
26.000
1126
26.000
1547
26.000
1969
26.000
2388
27.000
222
27.000
279
27.000
706
27.000
1134
27.000
1559
27.000
1985
27.000
2407
28.000
223
28.000
281
28.000
710
28.000
1141
28.000
1570
28.000
1999
28.000
2425
29.000
225
29.000
282
29.000
714
29.000
1149
29.000
1581
29.000
2014
29.000
2443
30.000
226
30.000
284
30.000
718
30.000
1156
30.000
1591
30.000
2027
30.000
2460
35.000
233
35.000
291
35.000
737
35.000
1188
35.000
1638
35.000
2090
35.000
2538
40.000
238
40.000
297
40.000
753
40.000
1216
40.000
1679
40.000
2144
40.000
2605
45.000
243
45.000
302
45.000
767
45.000
1241
45.000
1715
45.000
2191
45.000
2664
50.000
248
50.000
306
50.000
780
50.000
1264
50.000
1748
50.000
2234
50.000
2717
55.000
252
55.000
310
55.000
791
55.000
1284
55.000
1777
55.000
2272
55.000
2764
60.000
255
60.000
314
60.000
802
60.000
1303
60.000
1804
60.000
2307
60.000
2808
65.000
259
65.000
318
65.000
812
65.000
1320
65.000
1829
65.000
2340
65.000
2848
70.000
262
70.000
321
70.000
821
70.000
1336
70.000
1851
70.000
2370
70.000
2885
aAspiration
times
for
Waste
Material
Types
III.
1,
III.
2,
and
III.
3
are
identical.
bNumbers
represent
the
number
of
layers
of
confinement.
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4.7
PAYLOAD
ASSEMBLY
REQUIREMENTS
This
subsection
describes
the
procedures
that
must
be
followed
to
assemble
a
payload
approved
and
qualified
for
transport
in
the
TRUPACT­
II
in
accordance
with
the
CH­
TRAMPAC.

The
parameters
described
in
previous
subsections
shall
be
evaluated
for
selection
of
a
payload.

The
CIN
number
shall
uniquely
identify
the
payload
container.
The
content
code
identifies
a
payload
shipping
category
per
the
CH­
TRUCON
document.
Whenever
applicable,
the
measured
parameters
(
weight,
fissile
material,
and
the
decay
heat)
shall
be
checked
against
the
limits
after
addition
of
the
measurement
error,
as
detailed
in
previous
subsections.

If
the
container
does
not
meet
any
of
the
limits,
it
shall
be
rejected
from
transport,
marked,
and
segregated.
If
all
requirements
are
satisfied
except
for
the
decay
heat
limit
or
flammable
VOC
limits,
the
container
can
be
assigned
to
a
test
category
and
can
be
qualified
for
transport
only
by
the
procedure
outlined
in
subsection
4.7.2
of
this
Certification
Plan
and
consistent
with
the
CHTRAMPAC

Only
waste
with
approved
content
codes
described
in
the
CH­
TRUCON
document
may
be
transported
in
the
TRUPACT­
II.
Shipping
categories
impose
restrictions
and
requirements
on
the
manner
in
which
a
payload
can
be
assembled
as
follows:

 
Payload
selection
shall
be
made
from
only
those
payload
containers
that
have
been
approved
for
shipment.
 
After
all
the
payload
parameters
have
been
quantified
and
verified
and
the
transport
requirements
are
satisfied,
the
shipping
category
must
be
confirmed.
 
Individual
containers
forming
a
payload
within
each
TRUPACT­
II
shall
belong
to
the
same
shipping
category
or
equivalent
categories
allowed
by
Appendix
2.4
of
the
CH­
TRU
Payload
Assemblies.
This
permits
the
management
of
different
waste
material
types,
different
payload
containers,
and
different
internal
packaging
configurations.
This
requirement
applies
to
drums
(
including
POCs),
SWBs,
and
TDOPs.
 
Payload
containers
with
different
shipping
categories
may
be
shipped
when
each
payload
container
demonstrates
compliance
with
the
flammability
index
(
FI).
A
payload
can
be
qualified
for
shipment
only
if
the
FI
of
each
payload
container
is
equal
to
or
less
than
50,000.
If
one
or
more
payload
containers
fail
the
FI
requirements,
the
payload
assembly
shall
be
reconfigured
until
all
payload
packages
satisfy
this
requirement.
The
FI
is
calculated
as
the
ratio
of
the
actual
flammable
gas
generation
rate
to
the
allowable
flammable
gas
generation
rate
limit
multiplied
by
50,000.
 
Transportation
parameters
of
individual
payload
containers
are
recorded
on
the
PCTCD
or
OPCTCD
and/
or
the
TRUPACT­
II
test
category
payload
container
data
sheets.
Separate
PCTCD
and
OPCTCD
forms
are
used
for
the
analytical
payload
shipping
category
and
the
test
payload
shipping
category.
(
Examples
of
these
forms
are
provided
in
appendices
B­
1,
B­
2,
and
C,
respectively.)
Information
on
these
forms
should
be
available
for
each
payload
container,
even
if
the
format
is
not
identical
to
that
shown
in
appendices
B­
1
through
B­
4
and
C
(
e.
g.,
use
of
a
computer­
generated
form
is
acceptable
provided
all
required
information
is
included).
A
payload
container
may
be
certified
for
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HANFORD
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transport
only
if
all
transportation
parameters
are
in
compliance
with
the
CH­
TRAMPAC.
The
TCO
verifies
compliance
before
containers
are
authorized
for
transport.
 
A
TRUPACT­
II
shipment
is
authorized
only
if
all
the
transportation
requirements
are
met
and
verified
by
the
TCO.
The
transportation
parameters
of
every
TRUPACT­
II
shipment
are
then
recorded
on
the
PATCD
(
shown
in
Appendix
D).
The
information
on
this
form
must
be
available
for
each
payload
assembly,
even
if
the
format
is
not
identical
to
that
shown
in
Appendix
D
(
e.
g.,
use
of
a
computer­
generated
form
is
acceptable
provided
all
required
information
is
included).
The
shipper
shall
maintain
the
shipping
records
for
a
minimum
period
of
three
years.

All
authorized
payloads
must
meet
the
requirements
set
forth
in
the
CH­
TRAMPAC.
Data
on
the
parameters
for
specific
payloads
are
obtained
by
the
methods
outlined
in
this
Certification
Plan
in
accordance
with
the
specific
limits
of
the
CH­
TRUCON
document.
The
following
subsections
describe
methods
for
evaluating
the
payload
container
and
shipment
data
against
TRUPACT­
II
limits
and
restrictions.
All
container
and
shipment
data
are
entered
into
WWIS
and
must
be
approved
by
CBFO.

4.7.1
Certification
of
Individual
Payload
Containers
for
Transport
in
the
TRUPACT­
II
(
Analytical
Payload
Shipping
Category)

4.7.1.1
Requirements
Generating
and
storage
sites
shall
qualify
an
individual
payload
container
for
transport
in
a
TRUPACT­
II
under
the
analytical
category
by
verifying
that
the
container
meets
the
parameter
requirements/
limits
listed
in
previous
subsections
of
this
certification
plan.
All
parameters
noted
on
the
PCTCD
or
OPCTCD
for
overpack
containers
shall
be
included
in
any
modified
version.
Data
on
the
parameters
for
specific
payloads
shall
be
obtained
by
the
methods
outlined
in
this
Certification
Plan,
be
consistent
with
the
CH­
TRAMPAC
and
shall
be
consistent
with
the
information
for
each
parameter
provided
in
the
CH­
TRUCON
document.

Individual
payload
containers
must
be
qualified
for
transport
in
a
TRUPACT­
II
by
verifying
that
each
container
meets
the
requirements
and
limits
for
the
parameters
listed
on
the
PCTCD
or
OPCTCD
for
overpacks
for
the
analytical
payload
shipping
category.

4.7.1.2
Compliance
and
Verification
The
TCO
completes
a
PCTCD
or
OPCTCD
for
analytical
category
waste
in
accordance
with
WMP­
400,
Section
2.1.5,
to
qualify
an
individual
payload
container
for
shipping.
The
TCO
signs
and
dates
the
PCTCD
or
OPCTCD
after
verifying
that
each
container
meets
the
following
transportation
parameter
requirements.

 
Container
ID
and
container
Bar
Code
Numbers­­
identification
numbers
unique
to
each
container
and
used
to
track
process
data
and
package
history
 
Shipping
Category­­
assigned
using
the
corresponding
tables
in
the
CH­
TRUCON
document
or
as
approved
by
the
WIPP
CH­
TRU
Payload
Engineer
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HANFORD
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CERTIFICATION
PLAN
 
Content
Code­­
acquired
either
from
the
data
package
(
preassigned)
or
by
correlating
the
waste
description
with
the
applicable
contents
code
list
in
the
CH­
TRUCON
document
 
Container
Type
and
Configuration
(
e.
g.,
direct
load
or
overpacked
or
fixed)
 
obtained
by
visual
inspection,
RTR,
or
VE
 
Certification
Site­­
the
location
at
which
transportation
takes
place
(
e.
g.,
the
generating
site
for
newly
generated
waste;
the
generating
or
storage
site
for
retrievably
stored
waste)
 
CH­
TRAMPAC/
Transportation
Parameters­­
for
each
payload
container,
the
following
criteria
must
be
met:

1.
Residual
liquids
limited
to
residual
amounts
less
than
1
percent
of
container
volume
(
no
residual
liquids)

2.
Sharp/
heavy
objects
are
blocked/
braced/
suitably
packaged
3.
Nonradioactive
pyrophorics
are
prohibited
4.
Radioactive
pyrophorics
are
<
1%
by
weight
5.
Explosives
are
prohibited
6.
Corrosives
are
prohibited
7.
Pressurized
containers
and
compressed
gases
are
prohibited
8.
Sealed
containers
greater
than
4
liters
are
prohibited,
except
for
waste
material
Type
II.
2
packaged
in
metal
cans
9.
Rigid
liner
(
if
present)
is
punctured/
filtered
10.
Flammable
VOCs
are
limited
to
not
more
than
500
ppm
per
payload
container
or
be
evaluated
for
meeting
the
requirements
of
the
test
category
(
see
Subsection
4.7.2.2
of
this
Certification
Plan)

11.
Radiation
dose
rates
are
less
than
or
equal
to
the
limits
specified
in
Subsection
4.4.2.1,
Table
4.4­
2
of
this
Certification
Plan.

12.
Filter
Identification
 
Information
obtained
by
visual
inspection
includes
filter
vent
identification
of
both
supplier
and
date
of
installation,
lot
number,
or
unique
serial
number.
The
type
and
number
of
filters
will
be
documented
depending
on
container
type.
For
fixed
configurations
(
e.
g.,
pipe
overpacks),
the
filter
information
shall
be
documented
for
both
the
payload
containers
(
e.
g.,
inner
pipe
component
and
outer
drum).

13.
A
single,
unvented
heat­
sealed
bag
is
allowed
provided
the
requirements
of
Appendix
6.13
of
the
CH­
TRU
Payload
Appendices
are
met.
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HANFORD
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Measured
Transportation
Parameters
 
Weight­­
the
maximum
weight
limit
for
the
appropriate
payload
container
type
shall
be
recorded.
Loaded
weight
of
each
payload
container
obtained
from
the
data
package.
Container
weight
(
plus
error
at
one
standard
deviation)
is
obtained
from
the
data
package
(
an
error
is
assigned
to
the
container
weight
in
accordance
with
the
project
method)
and
total
weight
plus
error
compared
against
the
allowable
limit
for
each
payload
container.
If
overpacked,
the
maximum
allowable
limit
applies
to
the
outermost
payload
container.
 
Decay
Heat
(
Plus
Error)­­
obtained
and
recorded
from
the
data
package.
Decay
heat
plus
error
(
at
one
standard
deviation)
is
compared
against
the
allowable
decay
heat
limit
per
payload
container
for
applicable
shipping
category.
For
mixed
category
and/
or
taking
credit
for
dunnage,
the
decay
heat
limit
is
marked
N/
A,
and
the
flammability
index
is
used
and
recorded.
 
Fissile
Mass
(
Plus
Two
Times
the
Error)­­
obtained
from
NDA
data
report
(
fissile
mass
calculated
by
combining
isotopic
inventory
data
and
239Pu
FGE
for
each
radionuclide
in
the
waste,
plus
error
(
at
one
standard
deviation)
is
assigned
to
the
fissile
mass
for
the
appropriate
payload
container.
If
overpacked,
the
allowable
limit
applies
to
the
outermost
payload
container.
 
Curie
Limits
 
obtained
and
recorded
from
the
NDA
data
reports,
as
applicable,
for
only
S200
POCs.
The
measured
curie
value
plus
measurement
error
(
one
standard
deviation)
must
meet
the
appropriate
limit.

Unvented
Waste
Parameters
 
Aspiration
Method
(
Option
1,
2a,
2b,
or
3)­­
confirms
that
the
requirements
on
aspiration
time
for
containers
that
have
been
closed
(
e.
g.,
not
vented
with
an
approved
filter
vent)
for
a
period
of
time
are
met.
Aspiration
methods
must
be
determined
and
recorded.
Aspiration
methods
include:

1.
Required
Aspiration
Period­
The
required
aspiration
time
for
the
selected
option
shall
be
noted
or
determined
in
accordance
with
Appendix
3.7
of
the
CH­
TRU
Payload
Appendices.
If
the
hydrogen
concentration
indicates
that
aspiration
is
not
needed,
a
zero
shall
be
entered.

2.
Container
Closed
Time
(
Option
1)
 
the
period
of
time
a
payload
container
has
been
unvented
in
storage.
That
time
is
recorded.

3.
Headspace
H2
Concentration
(
Option
2a,
2b,
or
3)
 
The
H2
concentration
measured
in
the
headspace
of
a
payload
container
is
recorded.

4.
Aspiration
Period/
Aspiration
Table
 
Aspiration
time
selected
shall
be
limited
to
the
value
specified
by
appropriate
aspiration
table.
If
H2
concentration
indicates
the
aspiration
is
not
needed,
a
zero
is
recorded
on
the
PCTCD.
This
is
not
applicable
for
test
category
containers
or
overpacked
containers.
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HANFORD
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5.
Time
Container
Vented
 
Indicates
the
number
of
days
the
payload
container
has
vented.
The
time
that
the
container
was
vented
must
comply
with
the
prescribed
aspiration
period
recorded
above.

Overpack
Payload
Container
Parameters
Identification
Parameters
 
Overpack
Container
ID
Number/
Bar
Code
Number
 
The
site­
specific
ID
number
is
unique
to
each
container
of
waste
and
provides
a
means
for
tracking
process
data
records
and
package
history.
 
Payload
Shipping
Category
Number
 
The
governing
shipping
category
for
the
overpack
configuration
shall
be
determined
by
selecting
the
payload
shipping
category
of
the
container
being
overpacked
with
either
the
lowest
decay
heat
limit
or
the
lowest
hydrogen/
flammable
gas
generation
rate
limit.
These
values
shall
be
determined
by
consulting
the
appropriate
PCTCDs
completed
for
the
payload
container(
s)
to
be
overpacked.
 
Decay
Heat
Limit
 
The
maximum
allowable
decay
heat
per
payload
container
for
the
governing
payload
shipping
category
of
the
overpacked
configuration.
If
mixing
shipping
categories
within
an
overpack,
indicate
that
the
decay
heat
limit
for
the
payload
is
not
applicable.
Mixing
of
shipping
categories
shall
meet
the
requirements
of
Section
4.7.4.
 
Hydrogen/
Flammable
Gas
Generation
Rate
Limit
 
the
governing
flammable
gas
generation
rate
limit
for
the
overpack
is
recorded
either
from
an
approved
shipping
category
or
from
the
test
category
container
data
sheet.
If
mixing
shipping
categories
within
an
overpack,
indicate
that
the
hydrogen/
flammable
gas
generation
rate
limit
for
the
payload
is
not
applicable.
Mixing
of
shipping
categories
shall
meet
the
requirements
of
Section
4.7.4.
 
Overpack/
Overpacked
Container
Type
 
Select
the
appropriate
overpack
container
type
and
overpacked
container
type.
The
payload
container
shall
be
one
of
the
approved
types
in
one
of
the
following
authorized
configurations.

1.
SWB
with
55­
gallon
drum(
s)
(
SWB
overpack)
 
Waste
packaged
in
55­
gallon
drum(
s)
overpacked
in
one
SWB
(
up
to
four
55­
gallon
drums
per
SWB)

2.
TDOP
with
55­
gallon
drums
 
Waste
packaged
in
55­
gallon
drum(
s)
overpacked
in
one
TDOP
(
up
to
ten
55­
gallon
drums
per
TDOP)

3.
TDOP
with
SWB
 
Waste
packaged
in
one
SWB
overpacked
in
one
TDOP
(
one
SWB
per
TDOP)

4.
TDOP
with
SWB
overpack
 
Waste
packaged
in
55­
gallon
drum(
s)
overpacked
in
one
SWB
(
up
to
four
55­
gallon
drums
per
SWB)
overpacked
in
one
TDOP
(
one
SWB
per
TTDOP).
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HANFORD
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5.
TDOP
with
85­
gallon
drum
overpack(
s)
 
Waste
packaged
in
one
55­
gallon
drum
overpacked
in
one
85­
gallon
drum
overpacked
in
one
TDOP
(
up
to
six
85­
gallon
drum
overpacks
per
TDOP)

6.
TDOP
with
85­
gallon
drum(
s)­
Waste
packaged
in
85­
gallon
drum(
s)
overpacked
in
one
TDOP
(
up
to
six
85­
gallon
drums
per
TDOP).

7.
TDOP
with
bin
overpack
 
Waste
packaged
in
one
bin
overpacked
in
one
SWB
overpacked
in
one
TDOP
(
one
bin
overpack
per
TDOP).

8.
85­
gallon
drum
with
55­
gallon
drum
(
85­
gallon
drum
overpack).

 
Weight
Limit
 
The
maximum
allowable
weight
limit
for
the
appropriate
overpacking
payload
container
type
(
i.
e.,
SWB
or
TDOP)
shall
be
recorded.
The
limit
applies
only
to
the
outermost
payload
container.
 
Fissile
Mass
Limit
 
The
maximum
allowable
fissile
mass
limit
for
the
appropriate
payload
container
type
(
i.
e.,
SWB
or
TDO)
shall
be
recorded.
 
Certification
Site
 
The
certification
site
shall
be
recorded
at
the
location
at
which
transportation
certification
occurs.
 
Content
Code
 
The
content
code
from
the
data
package
for
the
payload
container
shall
be
approved.

CH­
TRAMPAC
Transportation
Parameters
Compliance
information
for
the
CH­
TRAMPAC
transportation
parameters
shall
be
obtained
from
the
data
package
for
the
payload
container.
The
TCO
indicates
compliance
and
documents
it
on
the
OPCTCD
as
appropriate.
The
following
criteria
shall
be
met.

 
Radiation
Dose
Rate
Less
Than
or
Equal
to
the
limits
specified
in
Subsection
4.4.2.1,
Table
4.4­
2
of
this
Certification
Plan
 
The
limit
applies
only
to
the
outermost
payload
container.
If
an
SWB
overpack
will
be
overpacked
in
a
TDOP,
the
limit
for
radiation
dose
rate
applies
only
to
the
TDOP.
 
Filter
Identification­­
If
a
payload
container
will
be
overpacked,
the
limit
applies
to
only
the
outermost
payload
container.
The
number
of
filters
will
be
documented
depending
on
container
type.
For
fixed
configurations
(
e.
g.,
pipe
overpacks),
the
filter
information
shall
be
documented
for
both
the
payload
containers
(
e.
g.,
inner
pipe
component
and
outer
drum).

Overpacked
Container
Measured
Parameters
 
Overpacked
Container
ID
Number
 
List
the
site­
specific
identification
number
for
each
of
the
overpacked
payload
containers.
 
Measured
Weight
and
Measurement
Error
 
The
measured
weight
and
measurement
error
(
one
standard
deviation)
for
each
overpacked
payload
container
or
the
entire
overpack
configuration
shall
be
recorded
and
is
limited
to
the
outermost
container
configuration.
The
measured
weight
and
measurement
error
may
be
obtained
from
PCTCD(
s)
or
HNF­
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HANFORD
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OPCTCD
for
each
overpacked
payload
container.
The
measured
weight
of
the
individual
overpacked
payload
containers
is
not
required
if
the
entire
overpack
configuration
will
be
weighed.
If
the
weight
of
each
individual
overpacked
payload
container
is
recorded,
enter
the
weight
and
measurement
error
(
one
standard
deviation)
of
the
empty
overpack
payload
container
on
the
last
row.
Calculate
the
total
weight
as
the
sum
of
each
of
the
individual
weights
(
including
the
weight
of
the
empty
overpack
container),
and
record
this
value
in
the
appropriate
box.
Calculate
the
root­
mean
square
(
RMS)
1
error
for
the
overpack
configuration
as
the
square
root
of
the
sum
of
the
squares
of
the
individually
listed
errors,
and
record
this
value
in
the
appropriate
box.
If
the
entire
overpack
configuration
is
weighed,
record
the
total
weight
of
the
overpack
configuration
and
the
measurement
error
(
one
standard
deviation)
in
the
appropriate
boxes
(
in
this
case,
the
measurement
error
is
the
same
as
the
RMS
[
calculated
as
RSS]
error).
 
Measured
Decay
Heat
and
Measurement
Error
 
The
measured
decay
heat
value
and
measurement
error
(
one
standard
deviation)
for
each
overpacked
analytical
category
payload
container
shall
be
recorded.
The
measured
decay
heat
value
and
measurement
error
may
be
obtained
from
the
PCTCD(
s)
or
OPCTCD
for
each
overpacked
payload
container.
For
analytical
category
payload
containers,
the
decay
heat
value
plus
the
measurement
error
for
each
payload
container
shall
be
compared
individually
to
the
governing
decay
heat
limit
for
the
overpacked
configuration.
 
Decay
heat
Limit
 
For
analytical
category
payload
containers,
the
maximum
allowable
decay
heat
limit
per
overpacked
payload
container
for
the
applicable
payload
shipping
category
shall
be
recorded
from
the
PCTCD(
s)
or
OPCTCD.
The
decay
heat
limits
are
recorded
for
use
in
determining
the
governing
decay
heat
limit.
 
Measured
Fissile
Mass
(
FGE)
and
Measurement
Error
 
The
measured
fissile
mass
and
two
times
the
measurement
error
(
two
standard
deviations)
for
each
payload
container
shall
be
recorded
as
obtained
from
the
PCTCD(
s)
or
OPCTCD
for
each
overpacked
payload
container.
The
subtotal
fissile
mass
plus
the
total
RMS
(
calculated
as
RSS)
error
(
RMS
[
calculated
as
RSS]
of
twice
each
individual
measurement
error)
or
the
entire
overpack
configuration
shall
be
compared
to
the
maximum
allowable
fissile
mass
limit
for
the
outermost
payload
container
of
the
overpack
configuration
(
i.
e.,
325
FGE
per
SWB
or
per
TDOP).
 
Hydrogen/
Flammable
Gas
Generation
Rate
 
The
hydrogen/
flammable
gas
generation
rate
for
each
overpacked
test
category
payload
container
shall
be
recorded.
The
hydrogen/
flammable
gas
generation
rate
limit
for
each
payload
container
(
analytical
or
test
category)
shall
be
recorded
for
later
use
in
completing
the
PATCD.
For
test
category
payload
containers,
the
hydrogen/
flammable
gas
generation
rate
for
each
payload
container
shall
be
compared
individually
to
the
governing
hydrogen/
flammable
gas
generation
rate
limit.
 
Hydrogen/
Flammable
Gas
Generation
Rate
Limit
 
For
test
category
and
analytical
category
payload
containers,
the
hydrogen/
flammable
gas
generation
rate
limit
per
1
Use
of
the
term
"
root­
mean­
square"
or
"
RMS"
is
calculated
as
"
root­
sum­
of­
squares"
or
"
RSS."
Whenever
a
WIPP
or
TRU
document,
form,
or
software
references
RMS,
this
shall
be
interpreted
to
mean
RSS.
HNF­
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HANFORD
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PLAN
overpacked
payload
container
for
the
applicable
payload
shipping
category
shall
be
recorded
from
the
PCTCD(
s).
The
hydrogen/
flammable
gas
generation
rate
limits
are
recorded
for
use
in
deterring
the
governing
limit.
 
Flammability
Index
(
FI)­
If
mixing
shipping
categories
within
an
overpack,
calculate
the
FI
for
each
overpack
container
as
directed
in
Appendix
2.4
of
the
CH­
TRU
Payload
Appendices
after
selecting
the
overpacking
containers
comprising
the
payload
assembly.
Calculation
is
typically
performed
by
a
verified/
validated
software
package.
FI
is
only
applicable
to
overpacking
payload
containers
of
different
shipping
categories.
For
overpacked
payload
containers
belonging
to
the
same
shipping
category,
indicate
the
FI
is
not
applicable.

Approved
for
Transport­­
the
TCO
records
and
signs
and
dates
the
PCTCD
or
OPCTCD
certifying
that
the
requirements
for
the
transportation
parameters
are
met.
If
the
requirements
are
not
met,
the
payload
container
is
rejected
(
nonconformance
disposition)
and
not
qualified
for
shipment.

Payload
containers
that
do
not
comply
with
parameter
limits
are
not
qualified
for
shipment.
These
containers
are
segregated
and
corrective
action
is
taken
to
resolve
the
noncompliant
condition.
The
TCO
completes
the
verification
and
certification
of
parameters
in
accordance
with
WMP­
400,
Section
2.1.5.

Refer
to
Appendix
A,
column
"
CH­
WAC
and
Certification
Plan
Section,"
rows
3.3.4
and
3.6.2,
which
contain
the
titles
of
applicable
procedures
that
implement
the
requirements
of
this
subsection.

4.7.2
Certification
of
Individual
Payload
Containers
for
Transport
in
the
TRUPACT­
II
(
Test
Payload
Shipping
Category)

4.7.2.1
Requirements
In
accordance
with
the
CH­
TRAMPAC,
Section
6.2,
payload
containers
assigned
to
the
test
category
must
meet
additional
criteria
for
certification.
The
generating
and
storage
sites
shall
qualify
an
individual
payload
container
for
transport
in
a
TRUPACT­
II
under
the
test
category
by
verifying
the
container
meets
the
parameter
requirements/
limits
in
this
subsection
and
in
section
6.2
of
the
CH­
TRAMPAC.

Complete
the
PCTCD
or
OPCTCD
for
the
test
payload
shipping
category
as
outlined
in
subsection
4.7.2.2
of
this
Certification
Plan.

Additional
requirements
for
the
test
payload
shipping
category
include
measurement
or
testing
of
55­
gallon
drums.
Drum
testing
of
55­
gallon
drums
shall
be
documented
in
the
TRUPACT­
II
test
category
payload
container
data
sheet
(
appendices
B­
3
and
B­
4
of
this
Certification
Plan).
HNF­
2600,
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HANFORD
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PLAN
Compliance
can
be
achieved
by
measurement
or
drum
testing.
Methods
must
be
consistent
with
the
CH­
TRAMPAC
in
the
following
sections:

 
Unified
flammable
gas
test
procedure
(
UFGTP)
 
Section
5.2.5
of
CH­
TRAMPAC
1.
Measurement
of
UFGTP
requirements
are
described
in
Section
5.2.5.2
of
the
CH­
TRAMPAC.

2.
Testing
of
UFGTP
requirements
is
described
in
Section
5.2.5.2
of
the
CH­
TRAMPAC.

3.
Data
sheets
for
documenting
test
results
are
identified
in
Appendixes
B­
3
and
B­
4
of
this
Certification
Plan.

 
Determination
of
flammable
gas/
VOC
concentrations
­
Appendix
3.10
of
the
CH­
TRU
Payload
Appendices.

1.
Compliance
with
calculations
of
drum
mathematical
models
and
methodology
are
described
in
Appendix
3.10
of
the
CH­
TRU
Payload
Appendices.

2.
Compliance
with
flammability
assessment
methodology
program
(
FAMP)
is
described
in
Appendix
3.10
of
the
CH­
TRU
Payload
Appendices.

4.7.2.2
Compliance
and
Verification
With
the
exception
of
waste
type
IV
(
solidified
organics),
which
currently
is
test
category
waste
by
definition,
the
Hanford
site
will
repackage
test
category
waste
into
an
acceptable
configuration
to
qualify
as
analytical
category
waste
or
conduct
appropriate
drum
measurements
or
testing
as
specified
in
Section
6.2
of
the
CH­
TRAMPAC.
Section
5.2.5
of
the
CH­
TRAMPAC
will
be
implemented
under
the
gas
generation
QAPP
and
HNF­
2599
for
gas
generation
testing.
Appendix
3.10
of
the
CH­
TRU
Payload
Appendices
will
be
implemented
via
e­
TRAMAPC
in
WWIS.
WWIS
entries
will
be
in
accordance
with
WMP­
400,
Section
7.1.5.
For
type
IV
waste
or
test
category
waste
that
cannot
be
repackaged,
the
Hanford
site
will
segregate
and
store
this
waste
until
testing
and/
or
repackaging
can
be
performed.

All
test
category
parameter
requirements
will
be
documented
in
accordance
with
Section
6.2
of
the
CH­
TRAMPAC.
Where
applicable,
overpacked
containers
parameter/
requirements
limits
will
be
documented
on
the
OPCTCD
in
accordance
with
Section
6.2
of
the
CH­
TRAMPAC.
The
TCO
completes
the
verification
and
certification
of
the
CH­
TRAMPAC
requirements
in
accordance
with
WMP­
400,
Section
2.1.5.

Refer
to
Appendix
A,
column
"
CH­
WAC
and
Certification
Plan
Section,"
rows
3.3.7
and
3.5.2,
which
contain
the
titles
of
applicable
procedures
that
implement
the
requirements
of
this
subsection.
HNF­
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REV
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HANFORD
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4.7.3
Assembly
of
a
TRUPACT­
II
Payload
4.7.3.1
Requirements
In
accordance
with
the
Section
6.2.2
of
the
CH­
TRAMPAC,
certified
payload
containers
shall
be
assembled
into
acceptable
TRUPACT­
II
payloads.
Total
TRUPACT­
II
package
limits
must
be
met
by
ensuring
the
TRUPACT­
II
SAR
restrictions
and
requirements
are
met,
and
by
evaluating
the
data
from
the
individual
PCTCDs
or
OPCTCDs,
as
applicable.

All
parameters
shall
be
met
and
documented
on
the
PATCD
consistent
with
subsection
4.7.3.2
of
this
Certification
Plan.

Weight
of
pallets,
reinforcing
plates,
slip­
sheets,
guide
tubes,
banding
material,
etc.,
shall
be
measured
for
total
weight
(
or
265
lbs)
and
recorded
on
the
PATCD
as
required.

4.7.3.2
Compliance
and
Verification
The
TCO
generates
a
PATCD
from
WWIS
upon
verifying
the
applicable
transportation
parameters
are
met,
consistent
with
WMP­
400,
Section
2.1.5.
The
parameters
listed
below
correspond
with
data
fields
on
the
PATCD,
consistent
with
WMP­
400,
Section
2.1.5.
When
assembling
payloads
with
mixed
shipping
categories,
each
payload
container
must
meet
all
parameters
provided
in
WWIS
(
e.
g.,
edit/
limit
checks
must
be
satisfied
before
a
payload
container
is
shippable).
The
WWIS
entries
must
be
done
in
accordance
with
WMP­
400,
Section
7.1.5.
The
parameters
listed
below
correspond
with
data
fields
on
the
PATCD
as
identified
in
WMP­
400,
Section
2.1.5,
and
shall
be
completed
as
follows.

 
Shipment
No.:
The
shipment
number
assigned
by
TCO.
 
TRUPACT­
II
OCA
Body/
Lid
Nos.:
The
identification
numbers
on
the
TRUPACT­
II
OCA
body
and
lid.
 
Payload
Shipping
Category:
The
governing
shipping
category
of
the
payload
shall
be
recorded
only
if
all
containers
belong
to
the
same
or
equivalent
shipping
category.
Mixing
shipping
categories
is
also
allowed
in
a
TRUPACT­
II
or
CH­
TRAMPAC,
but
must
be
consistent
with
WWIS(
e.
g.,
all
edit/
limit
checks
are
satisfied).
 
Category
Decay
Heat
Limit:
If
all
containers
belong
to
the
same
or
equivalent
shipping
category,
the
maximum
allowable
decay
heat
per
payload
container
for
the
governing
payload
shipping
category
shall
be
recorded
from
the
PCTCD
and
OPCTCD.
Mixing
of
shipping
categories
and
payloads
of
any
authorized
contents,
including
credit
for
dunnage,
is
allowable
provided
all
parameters
in
provided
in
WWIS
are
met
(
e.
g.,
all
edit/
limit
checks
are
satisfied).
 
Transportation
Packaging:
The
type
of
packaging
used
(
TRUPACT­
II)
shall
be
recorded.
The
payload
configuration
shall
consist
of
any
approved
type
of
payload
container
(
verified
by
visual
inspection).
 
Hydrogen/
Flammable
Gases
Rate
Limit:
If
all
containers
belong
to
the
same
or
equivalent
shipping
category,
the
maximum
allowable
hydrogen/
flammable
gas
generation
rate
per
payload
container
for
the
governing
payload
shipping
category
shall
be
recorded
from
PCTCD(
s).
Mixing
of
shipping
categories
is
also
allowed
in
the
HNF­
2600,
REV
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HANFORD
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TRANSURANIC
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CERTIFICATION
PLAN
TRUPACT­
II
or
CH­
TRAMPAC,
but
must
be
consistent
with
WWIS
(
e.
g.,
all
edit/
limit
checks
are
satisfied).
 
Type
of
Payload:
The
payload
configuration
shall
consist
of
an
approved
type
of
payload
container.
If
the
payload
type
is
"
Standard
Pipe
Overpack"
each
seven­
pack
in
the
payload
must
be
comprised
of
only
6­
inch
standard
pipe
overpacks
or
12­
inch
standard
pipe
overpacks.
 
Date
ICV
Closed:
Identifies
the
date
the
inner
containment
vessel
is
closed
and
that
information
is
recorded.
 
Payload
Composition:
Identifies
the
following
container
parameters:

1.
Payload
container
identification
number
(
or
"
DUNNAGE"
or
"
EMPTY")

2.
Weight
and
measurement
error
3.
Decay
heat
and
measurement
error
of
one
standard
deviation
4.
FGE
and
two
times
the
measurement
error
(
two
standard
deviations
or
one
times
RMS
[
calculated
as
RSS]
error
if
values
are
taken
from
an
OPCTCD)

5.
Measured
hydrogen
flammable
gas
generation
rate
6.
Calculated
flammability
index
for
mixed
shipping
categories
in
accordance
with
WWIS.

Weights,
decay
heats,
and
FGEs
of
individual
containers
are
summed
for
both
top
and
bottom
layers
of
the
assembly,
and
the
total
error
for
each
parameter
is
calculated
as
indicated
on
the
PATCD.

Payload
Totals
 
The
total
weight
of
pallets,
reinforcing
plates,
slip­
sheets,
guide
tubes,
banding
material,
etc.,
(
or
265
pounds)
shall
be
measured
and
recorded.
 
Total
Weight
(
Plus
RMS
[
calculated
as
RSS]
Error)
of
Payload
and
Package­­
Indicates
that
the
total
weight
of
the
payload
and
package
does
not
exceed
limits
established
in
the
CH­
TRAMPAC.
The
total
error
can
be
determined
by
weighing
the
entire
payload
assembly.
 
Bottom
Layer
(
Plus
RMS
[
calculated
as
RSS]
Error)
>
Top
Layer
(
Plus
RMS
[
calculated
as
RSS]
Error)­­
The
total
weight
of
the
bottom
layer
of
seven
drums,
seven
pipe
overpacks,
SWB,
or
five
drums
in
a
TDOP
must
be
verified
to
be
greater
than
or
equal
to
the
top
layer.
This
is
only
applicable
to
TRUPACT­
IIs.
 
Total
Weight
(
Plus
RMS
[
calculated
as
RSS]
Error)
<
7,265
lbs.
The
total
weight
plus
error
must
be
verified
to
be
less
than
or
equal
to
7,265
pounds.
 
Total
Decay
Heat
(
Plus
RMS
[
calculated
as
RSS]
Error)
of
all
Containers­­
Indicates
that
the
total
decay
heat
plus
error
for
all
containers
comprising
the
shipment
does
not
exceed
allowable
limits.
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Total
239Pu
FGE
(
Plus
RMS
[
calculated
as
RSS]
Error)
of
all
Containers­­
Indicates
that
the
calculated
total
fissile
quantity
plus
two
times
the
error
for
all
containers
comprising
the
shipment
does
not
exceed
allowable
limits.
 
Dose
Rates­­
Indicates
that
dose
rate
measurements
do
not
exceed
allowable
limits.

Payload
Certification
Parameters
 
Decay
Heat
Plus
Error
of
Each
Analytical
Category
Payload
Container
Less
Than
or
Equal
to
Governing
Decay
Heat
Limit:
For
payload
containers
with
the
same
of
equivalent
payload
shipping
category
shipped
under
a
governing
payload
shipping
category,
all
analytical
category
payload
containers
shall
meet
the
governing
decay
heat
limit.
 
Hydrogen/
Flammable
Gas
Generation
Rate
of
Each
Test
Category
Payload
Container
Less
Than
or
Equal
to
Governing
Hydrogen/
Flammable
Gas
Generation
Rate
Limit:
For
payload
containers
with
the
same
or
equivalent
payload
shipping
category
shipped
under
a
governing
hydrogen/
flammable
gas
generation
rate,
all
payload
containers
shall
meet
the
governing
hydrogen/
flammable
gas
generation
rate
limit.
 
Flammability
Index
of
Each
Payload
Container
Greater
Than
Zero
and
Less
Than
or
Equal
to
50,000
(
Section
6.2.4
of
the
CH­
TRAMPAC):
For
shipments
with
dunnage
or
multiple
shipping
categories,
record
the
FI
for
each
container,
calculated
as
described
in
Section
6.2.4
of
the
CH­
TRAMPAC
and
Appendix
2.4
of
the
CH­
TRU
Payload
Appendices.
The
FI
for
each
container
must
be
a
non­
negative
number
less
than
or
equal
to
50,000
for
the
payload
to
be
eligible
for
shipment.
 
Payload
Total
Gas
Release
Rate
Less
Than
or
Equal
to
Limit
Calculated
in
Accordance
With
Section
6.2.5
(
Section
6.2.5
of
the
CH­
TRAMPAC):
Payload
total
gas
release
rate
limits
apply
only
to
payloads
containing
one
or
more
Waste
Type
IV
payload
containers
that
exceed
the
payload
container
total
gas
release
rate
limit
specified
in
Table
5.2­
11
of
Section
5.2
of
the
CH­
TRAMPAC.
The
site
Transportation
Certification
Official
shall
verify
that
the
determined
payload
total
gas
release
rate
is
less
than
or
equal
to
the
appropriate
payload
total
gas
release
rate
limit
pursuant
to
the
methodology
defined
in
Section
6.2.5
of
the
CH­
TRAMPAC.
 
Bottom
Weight
Greater
Than
or
Equal
to
Top
Weight:
The
subtotal
weight
plus
subtotal
RMS
(
calculated
as
RSS)
weight
error
of
the
bottom
layer
of
seven
55­
gallon
drums,
seven
pipe
overpacks,
one
SWB,
five
55­
gallon
drums
in
a
TDOP,
or
three
85­
gallon
drums
in
a
TDOP
shall
be
greater
than
or
equal
to
that
of
the
top
layer.
 
Total
Weight
Plus
RMS
(
calculated
as
RSS)
Error
 
to
7,265
pounds.:
The
total
measured
payload
weight
plus
the
weight
of
the
pallets,
reinforcing
plates,
etc.,
plus
the
total
RMS
(
calculated
as
RSS)
weight
error
shall
be
less
than
or
equal
to
7,265
pounds.
 
Decay
heat
Plus
RMS
(
calculated
as
RSS)
Error
Less
Than
or
Equal
to
40
Watts:
The
total
measured
decay
heat
value
plus
the
total
RMS
(
calculated
as
RSS)
decay
heat
error
shall
be
less
than
or
equal
to
the
design
limit
for
the
packaging.
The
design
limit
for
the
TRUPACT­
II
is
40
watts.
 
Fissile
Mass
(
239Pu
FGE)
Plus
RMS
(
calculated
as
RSS)
Error
Less
Than
or
Equal
to
Payload
Limit:
The
total
measured
fissile
mass
(
239Pu
FGE)
plus
the
total
RMS
(
calculated
as
RSS)
fissile
mass
error
shall
be
less
than
or
equal
to
the
maximum
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allowable
fissile
mass
limit
established
for
the
payload
configuration.
If
the
payload
is
composed
of
only
pipe
overpacks
(
standard,
S100,
or
S200),
the
total
239Pu
FGE
limit
is
2,800
grams
per
TRUPACT­
II.
The
total
239Pu
FGE
limit
for
all
other
payloads
is
325
grams
per
TRUPACT­
II.
 
Total
Activity
plus
Error
for
S100
Pipe
Overpack
Payloads
Less
Than
or
Equal
to
406
Curies
(
Section
3.3):
The
total
activity
for
a
payload
assembly
made
up
of
S100
pipe
overpacks
plus
the
error
(
i.
e.,
one
standard
deviation)
shall
be
less
than
or
equal
to
406
Ci.
There
is
no
activity
limit
for
other
payloads.

The
TCO
completes
the
PATCD,
except
for
dose
rate
information,
and
provides
the
PATCD
to
loading
personnel.
Loading
personnel
load
the
TRUPACT­
II
in
accordance
WRP1­
OP­
0521.
The
TCO
signs
and
dates
the
PATCD
upon
verifying
the
TRUPACT­
II
transportation
requirements,
including
dose
rate
information,
are
met,
the
TRUPACT­
II
vessel
is
loaded,
and
the
payload
is
certified
for
transport.
This
is
done
in
accordance
with
WMP­
400,
Section
2.1.5.

Refer
to
Appendix
A,
column
"
CH­
WAC
and
Certification
Plan
Section,"
rows
3.2.1
and
3.6.2,
which
contain
the
titles
of
applicable
procedures
that
implement
the
requirements
of
this
subsection.

4.7.4
Mixing
of
Shipping
Categories
4.7.4.1
Requirements
Appendix
2.4
of
the
CH­
TRU
Payload
Appendices
describes
the
logic
for
mixing
shipping
categories
for
compliance
with
flammable
(
gas/
VOC)
concentration
limits,
including
the
determination
of
the
FI.

Mixing
of
shipping
categories
is
allowed
for
direct
loaded
and
overpacked
payload
configurations
by
ensuring
that
each
payload
container
or
overpacked
container
does
not
contain
a
flammable
mixture
of
gases.
Mixing
of
shipping
categories
is
allowed
only
within
authorized
payload
configurations
comprised
of
a
single
payload
container
type
as
listed
in
Section
3.2.1
of
the
CH­
TRAMPAC.
(
Note:
Standard
pipe
overpacks
may
be
assembled
in
a
TRUPACT­
II
payload
with
55­
gallon
drums.
Standard
pipe
overpacks
in
this
payload
assembly
are
considered
55­
gallon
drums
and
are
subject
to
the
requirements
of
Sections
4.4.1
and
4.7.1.)
Each
payload
container
or
overpacked
container
is
assessed
through
the
calculation
of
the
FI
for
the
container,
which
accounts
for
the
properties
of
each
of
the
other
containers
in
the
assembly
or
overpacked
configuration,
which
may
include
dunnage
containers.

A
payload
is
qualified
for
shipment
only
if
the
FI
of
each
payload
container
or
overpacked
container
is
a
non­
negative
number
less
than
or
equal
to
50,000.
If
one
or
more
containers
fail(
s)
the
FI
requirement,
the
payload
or
overpacked
configuration
shall
be
reconfigured
until
all
containers
satisfy
this
requirement.
Otherwise,
containers
not
meeting
the
FI
requirement
shall
be
placed
in
the
test
category
or
rejected
from
transport
and
subject
to
mitigation
or
repackaging.
The
FI
determination
can
be
performed
either
manually
or
by
the
use
of
a
verified/
validated
software
package.
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4.7.4.2
Compliance
and
Verification
For
test
category
payload
containers
and/
or
mixed
shipping
category
payload
containers
that
comprise
a
payload,
WWIS
will
be
used
to
determine
payload
shipability.
If
WWIS
edit/
limit
checks
are
satisfied,
a
payload
assembly
can
be
approved
for
shipment
provided
all
other
payload
container
requirements/
parameters
are
met
as
well.
WWIS
entries
will
be
done
in
accordance
with
WMP­
400,
Section
7.1.5.

5.0
QUALITY
ASSURANCE
PLAN
Each
site
must
develop
and
implement
QA
plans
for
TRU
waste
characterization,
certification,
and
packaging.
QA
plans
are
submitted
to
CBFO
for
approval
before
TRU
wastes
are
characterized,
certified,
and
transported
to
WIPP.
Analytical
laboratories
analyzing
waste
for
characterization
are
required
to
have
an
established
QA
program.
No
waste
may
be
certified
unless
it
is
a
product
of
a
waste
stream
evaluated
and
approved
by
CFBO.
The
TRUPACT­
II
is
not
used
without
CBFO
granting
authority.

The
QAPD
establishes
QA
program
requirements
for
all
programs,
projects,
and
activities
sponsored
by
permittee.
The
QA
plan
associated
with
the
certification
plan
must
apply
QAPD
requirements.
The
QA
requirements
for
compliance
with
TRUPACT­
II
loading
and
usage
are
derived
from
10
CFR
71,
Subpart
H,
"
Packaging
and
Transportation
of
Radioactive
Materials";
49
CFR
173,
"
Shippers
 
General
Requirements
for
Shipments
and
Packagings";
TRUPACT­
II
Certificate
of
Compliance;
DOE
O
460.1
and
460.2;
and
the
permittee
TRUPACT­
II
CH
Packaging
Program
Guidance,
Packaging
Operations,
and
Packaging
Maintenance
Manual
manuals.
The
QA
plan
for
packaging
must
address
DOT
and
NRC
requirements
applicable
to
the
use,
maintenance,
and
control
of
packages
used
to
transport
TRU
waste
to
WIPP,
including
the
criteria
addressed
in
10
CFR
71,
Subpart
H;
10
CFR
72,
"
Licensing
Requirements
for
the
Independent
Storage
of
Spent
Nuclear
Fuel
and
High­
Level
Radioactive
Waste,"
Subpart
G,
"
Quality
Assurance";
and
10
CFR
50,
"
Domestic
Licensing
of
Production
and
Utilization
Facilities,"
Appendix
B,
"
Quality
Assurance
Criteria
for
Nuclear
Power
Plants
and
Fuel
Reprocessing
Plants."

This
QA
plan
implements
the
combined
QA
requirements
for
certification,
transportation,
and
packaging
established
in
the
documents
identified
above.
HNF­
2599
implements
the
QA/
QC
activities
and
requirements
specified
in
the
WAP.
All
analytical
labs
analyzing
WIPP
waste
characterization
samples
shall
have
an
established
and
documented
QA/
QC
program.
Activities
included
in
the
scope
of
this
QA
plan
are
those
related
to
certifying
that
waste
containers
and
payload
assemblies
meet
the
criteria
and
requirements
specified
in
the
CH­
WAC,
CHTRAMPAC
TRUPACT­
II
Certificate
of
Compliance,
operation
and
maintenance
of
transport
containers,
waste
transportation
services,
and
the
criteria
specific
to
the
packaging
and
transportation
of
radioactive
materials.
This
QA
plan
ensures
that
all
activities
that
are
governed
by
the
CFRs,
applicable
certificates
of
compliance,
or
other
regulatory
requirements
are
conducted
in
accordance
with
written,
approved
procedures
or
instructions
that
incorporate
the
applicable
regulatory
requirements.
Activities
that
are
important
to
safety
are
performed
with
specified
equipment
under
suitable
conditions,
and
prerequisites
are
satisfied
before
inspection,
testing,
or
operation.
This
QA
plan
takes
precedence
over
any
other
Hanford
site
QA
plans
HNF­
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HANFORD
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PLAN
related
to
characterization
and
certification
of
TRU
wastes
destined
for
WIPP,
and
transportation
and
packaging
applicable
to
the
TRUPACT­
II.
This
plan
does
not
apply
to
the
procurement,
inspection,
or
testing
of
payload
containers
except
as
those
activities
apply
to
verification
that
the
payload
containers
meet
the
requirements
of
the
TRUPACT­
II
Certificate
of
Compliance.

Any
payload
container
with
unresolved
discrepancies
(
e.
g.,
CARs,
NCRs)
associated
with
hazardous
waste
characterization
will
not
be
shipped
to
WIPP
until
the
discrepancies
are
resolved
consistent
with
applicable
site­
specific
procedures
(
e.
g.,
WMP­
400,
Section
1.3.2
or
1.3.3).

The
organization
of
this
QA
plan
is
based
on
the
QAPD
elements
outlined
below.
Table
5­
1
provides
a
cross­
reference
of
identical
or
related
QA
requirement
elements
from
10
CFR
830.120
and
10
CFR
71.

 
Organization
and
QA
Program
documents
the
organizational
structure,
primary
interfaces
functional
responsibilities,
levels
of
authority,
and
lines
of
communication
for
activities
affecting
quality,
and
identifies
the
activities
and
items
to
which
the
QA
program
applies.
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Table
5.0­
1.
Cross­
Reference
of
Quality
Assurance
Requirements*
QAPD
and
QA
Plan
Section
Equivalent
Section
in
10
CFR
830.120
Equivalent
Section
in
10
CFR
Part
71,
Subpart
H
Organization
and
QA
Program
Program
QA
Organization
QA
Program
Personnel
Qualification
and
Training
Personnel
Training
and
Qualification
QA
Program
Quality
Improvement
Quality
Improvement
Corrective
Action
Nonconforming
Materials,
Parts,
or
Components
Documents
Records
Documents
and
Records
Document
Control
QA
Records
Work
Processes
Work
Processes
Instructions,
Procedures,
and
Drawings
Identification
and
Control
of
Materials,
Parts,
and
Components
Control
of
Special
Processes
Procurement
Procurement
Procurement
Document
Control
Control
of
Purchased
Material,
Equipment,
and
Services
Inspection
and
Testing
Work
Process
and
Acceptance
Testing
Internal
Inspection
Test
Control
Control
of
Measuring
and
Test
Equipment
Inspection,
Test,
and
Operating
Status
Handling,
Storage,
and
Shipping
Assessment
Requirements
Management
Assessment
Independent
Assessment
Audits
Sample
Control
Requirements
Work
Processes
Not
applicable
Scientific
Investigation
Requirements
Work
Processes
Design
Identification
and
Control
of
Materials,
Parts,
and
Components
Software
Requirements
Not
applicable
Not
applicable
*
The
TRU
Project
applies
a
graded
approach
for
managing
items
and
activities
associated
with
certifying
waste
for
shipment
to
WIPP
as
defined
in
WMP­
400,
Section
1.1.2,
"
TRU
Graded
Approach."

 
Personnel
Qualification
and
Training
identifies
the
Hanford
site
qualification
and
training
programs
and
plans
established
to
ensure
personnel
are
provided
training
to
perform
their
assignments
and
maintain
job
proficiency.
 
Quality
Improvement
describes
the
processes
to
detect
and
prevent
conditions
adverse
to
quality,
pursue
continuous
quality
improvement,
and
control
and
correct
nonconforming
items.
 
Documents
and
Records
describes
the
processes
for
preparation,
review,
approval,
issue,
use,
revision,
and
control
of
project
documents
and
records.
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Work
Processes
identifies
the
processes
by
which
work
conditions,
equipment,
and
special
processes
are
controlled
to
ensure
quality.
 
Procurement
identifies
the
technical
and
QA
requirements
for
procured
items
and
services.
 
Inspection
and
Testing
identifies
the
processes
for
inspection
and
testing.
 
Assessment
Requirements
describes
the
requirements
for
conducting
management
and
independent
assessments
to
measure
management
effectiveness,
item
quality,
and
process
effectiveness
and
to
promote
improvement.
 
Sample
Control
Requirements
identifies
the
requirements
for
the
control
of
waste
samples,
including
identification,
handling,
storing,
shipping,
and
archiving.
 
Scientific
Investigation
Requirements
describes
the
requirements
for
defining,
controlling,
verifying,
and
documenting
scientific
investigations.
 
Software
Requirements
specifies
the
requirements
for
developing,
procuring,
maintaining,
and
using
software.

5.1
ORGANIZATION
AND
QA
PROGRAM
This
QA
program
applies
to
items
and
activities
affecting
project
quality.
Effective
implementation
of
this
QA
program
is
dependent
on
the
efforts
at
all
levels
of
the
program
participants.
The
organizational
structures
and
the
responsibility
assignments
of
program
participants
shall
be
such
that
those
organizations
that
have
been
assigned
responsibility
for
performing
the
work
are
responsible
for
achieving
and
maintaining
quality.
Management
is
responsible
for
defining
quality,
developing
appropriate
plans
to
attain
quality,
and
supporting
the
workers
in
pursuit
of
quality.
The
QA
organization
is
responsible
for
verifying
the
achievement
of
quality
in
the
implementation
of
this
QA
program.
Organizational
responsibilities
are
shown
in
figure
2­
1.
Organizational
and
individual
responsibilities
for
TRU
waste
characterization,
assessment,
waste
transportation,
nuclear
safety,
environmental
protection,
and
management
and
operation
of
the
TRU
Project
are
addressed
in
section
2.0
of
this
Certification
Plan.

In
addition,
such
personnel
or
organizations
shall
(
1)
have
direct
access
to
responsible
management
at
a
level
where
appropriate
action
can
be
effected,
and
(
2)
report
to
a
management
level
such
that
required
authority
and
organizational
freedom
are
provided,
including
sufficient
independence
from
cost
and
schedule
consideration.

The
organizational
structure
and
responsibility
assignments
shall
be
such
that:

 
Quality
is
achieved
and
maintained
by
those
who
have
been
assigned
responsibility
for
performing
work,
and
 
Quality
achievement
is
verified
by
personnel
or
organizations
that
are
not
directly
responsible
for
performing
the
work.
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Additional
organization
and
QA
program
requirements
include
the
following:

1.
The
individual(
s)
or
organization(
s)
responsible
for
establishing
and
executing
a
QA
program
may
delegate
any
or
all
of
the
work
to
others
but
shall
retain
responsibility
therefore.

2.
Responsibility
for
the
control
of
further
processing,
delivery,
installation,
or
operation
of
nonconforming
items
shall
be
designated
in
writing.

3.
When
more
than
one
organization
is
involved
in
the
execution
of
activities
covered
by
this
Certification
Plan,
the
responsibility
and
authority
of
each
organization
shall
be
clearly
established
and
documented.

4.
The
external
interfaces
between
organizations
and
the
internal
interfaces
between
organizational
units,
and
changes
thereto,
shall
be
documented.

5.
Interface
responsibilities
shall
be
defined
and
documented.

All
personnel
involved
with
TRU
waste
certification,
packaging,
and
transportation
ensure
the
quality
of
their
activities
and
products.
If
work
is
delegated,
the
individual
making
the
delegation
retains
responsibility
for
the
delegated
work.
Disputes
related
to
QA
program
requirements
will
be
resolved
by
the
SQAO
and
cognizant
project
personnel.

TRU
project
management
at
all
levels
have
established
communication
channels
that
provide
timely
and
wide
dissemination
of
information
related
to
the
TRU
Project
quality
performance
which
includes:

 
QA
program
status
 
Lessons
learned
 
Quality
improvement
 
Results
of
trend
analysis.

The
program
interfaces
are
described
and
defined
in
section
2.0
of
this
certification
plan.

Figure
1­
1
(
see
section
1.0
of
this
Certification
Plan)
illustrates
the
hierarchy
and
interrelationships
of
QA
documents
governing
the
QA
program.
Quality
management
documents
are
audited
and/
or
assessed
to
ensure
they
meet
project
requirements.

The
TRU
Project
QA
organization
has
the
authority,
access
to
work,
and
organizational
freedom
to
identify
quality
problems,
make
recommendations
for
resolution,
and
verify
implementation
of
corrective
actions.
In
addition,
the
QA
organization
will
ensure
unsatisfactory
conditions
are
controlled
until
proper
corrective
actions
have
been
completed.

Project
personnel
plan
certification
activities
and
document
the
planning
process.
Planning
documentation
is
subject
to
review
by
facility
managers
and
subject
matter
experts
(
SME)
s.
Project
planning
documentation
consists
of
this
certification
plan,
HNF­
2599,
implementing
procedures,
training
plans,
and
facility
and
certification
process
designs.
These
documents
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establish
performance
criteria
and
methods
to
measure
performance
relevant
to
the
project.
All
project
personnel
are
accountable
for
ensuring
quality
within
their
assigned
areas
of
responsibility.
However,
the
SQAO
is
responsible
for
determining
the
effectiveness
of
this
QA
plan,
which
is
accomplished
through
internal
reporting
procedures,
audits,
and
assessments
(
see
subsection
5.3
of
this
Certification
Plan).

5.2
PERSONNEL
QUALIFICATION
AND
TRAINING
Personnel
performing
work
in
support
of
the
project
receive
QA
indoctrination
and
are
qualified
and
trained
to
ensure
that
suitable
proficiency
is
achieved
and
maintained
in
the
performance
of
their
assigned
tasks.
Records
documenting
qualifications
and
completed
training
programs
are
maintained
and
controlled
as
described
in
subsections
5.4
and
5.5
of
this
Certification
Plan.

5.2.1
Qualification
Facility
managers,
the
SPM,
and
the
Training
manager
determine
qualification
standards
for
each
job
category
relevant
to
the
project
and
ensure
that
qualifications
of
project
personnel,
including
minimum
education
and
experience,
have
been
verified.
Project
personnel
maintain
minimum
qualifications
in
accordance
with
WMP­
400,
Section
1.2.1,
"
TRU
Training
and
Qualification
Plan."
The
SPM
assists
facility
managers
in
determining
which
positions
relevant
to
the
project
require
minimum
qualifications.
The
period
of
effectiveness
for
qualification
associated
with
special
processes
and
operations
that
require
special
skills
and
the
requalification
criteria
are
specified
or
referenced
in
WMP­
400,
Section
1.2.1.
Facility
managers
ensure
auditable
records
documenting
personnel
qualifications
are
maintained
as
described
in
WMP­
400,
Section
1.5.1.
Records
of
qualified
personnel,
their
areas
of
qualification,
and
qualification
periods
(
as
appropriate)
are
retained
in
the
TRU
project
records
files.

5.2.2
Training
The
SPM
and
facility
managers
ensure
that
all
project
personnel
receive
indoctrination
and
training
on
the
scope,
purpose,
and
objectives
of
the
project
and
the
specific
QAOs
of
the
tasks
being
performed.
Facility
personnel
performing
activities
affecting
quality
are
trained
according
to
facility
training
plans
to
ensure
they
achieve
and
maintain
proficiency.
Personnel
receive
initial
and
continuing
training
requisite
with
their
activities
and
level
of
responsibility,
as
described
in
WMP­
400,
Section
1.2.1.

Training
is
designed,
developed,
conducted,
and
evaluated
in
accordance
with
Hanford
site
requirements
described
in
WMP­
400,
Section
1.2.1.
Training
programs
may
include
classroom
instruction;
practical
hands­
on
experience;
supervised
on­
the­
job
training;
self­
paced
individual
study;
and
written,
oral,
or
practical
demonstration
of
worker
competence.
Facility
managers
(
or
designees)
analyze
job
positions
and
determine
task
responsibilities
for
project
personnel
to
ensure
education,
experience,
and
training
is
commensurate
with
minimum
requirements
specified.
Facility
managers
are
responsible
for
ensuring
that
auditable
records
documenting
the
required
training
and
qualifications
are
maintained
in
accordance
with
WMP­
400,
Section
1.2.1.
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5.3
QUALITY
IMPROVEMENT
Project
personnel
continually
evaluate
and
improve
project
activities.
The
SQAO
ensures
that
quality
improvement
in
the
project
is
achieved
by
identifying
and
controlling
conditions
adverse
to
quality,
analyzing
trends,
reporting
and
tracking
nonconformances,
and
implementing
corrective
actions.
These
quality
improvement
activities
detect
and
prevent
unacceptable
quality
problems
and
thereby
increase
accuracy
and
reliability
and
reduce
variability.

A
condition
adverse
to
quality
is
an
all­
inclusive
term
used
in
reference
to
failures;
malfunctions;
deficiencies;
and
nonconforming
items,
materials,
parts,
or
components,
and
processes.
Project
personnel
ensure
that
nonconforming
items,
materials,
parts,
or
components,
waste
containers,
etc.,
are
adequately
identified
and
segregated
from
acceptable
items
and
materials
to
preclude
their
inadvertent
use.
The
SQAO,
the
SPM,
facility
managers,
and
FQAOs
have
the
authority
to
stop
certification,
packaging,
and
transportation
activities
and/
or
refuse
to
accept
work
products
or
services
(
e.
g.,
procured
items,
documentation,
packaging,
and
waste
shipments)
that
do
not
conform
to
project
requirements.
All
Hanford
site
employees
have
the
responsibility
to
stop
work
that
poses
a
clear
and
imminent
danger
to
the
safety
and
health
of
employees,
subcontractors,
visitors,
or
the
environment.
Project
personnel
report
conditions
adverse
to
quality
to
FQAOs
and/
or
the
SQAO,
who
ensure
that
the
condition
adverse
to
quality
is
investigated
and
that
corrective
action
is
taken
as
described
in
this
section.

All
violations
of
the
WIPP
Hazardous
Waste
Facility
Permit
must
be
managed
as
a
significant
condition
adverse
to
quality.
Project
personnel
notify
permittee
of
all
conditions
adverse
to
quality
affecting
waste
to
be
shipped
to
WIPP
and
forward
all
CARs
related
to
violations
of
the
WIPP
Hazardous
Waste
Facility
Permit
to
permittee
for
tracking.

Deficiencies
are
uncontrolled
and
unapproved
deviations
from
an
approved
plan,
procedure,
or
expected
result.
Deficiencies
specific
to
the
project
also
include
documentation
or
management
practices
that
do
not
meet
the
requirements
related
to
waste
certification,
packaging,
and
transportation,
which
are
identified
in
the
WAP,
CH­
TRAMPAC,
CH­
WAC,
QAPD,
DOE
orders,
and
applicable
federal
and
state
regulations.
Project
personnel
are
responsible
for
identifying
any
condition
that
affects
the
project's
compliance
with
these
requirements.
Assessments
may
often
identify
systems,
processes,
products,
or
services
that
do
not
meet
performance
criteria
established
in
planning
documents.
When
deficiencies
are
found,
project
personnel
take
prompt
action
to
rectify
the
situation.

Any
individual
who
identifies
a
condition
adverse
to
quality
initiates
an
NCR
or
CAR
in
accordance
with
WMP­
400,
Section
1.3.2
or
1.3.3.
If
the
safety
or
quality
of
the
certification
process
could
be
compromised
by
continued
use
of
a
nonconforming
item,
the
item
is
taken
out
of
service
and
tagged
or
otherwise
identified
to
prevent
reuse
or
acceptance
until
the
nonconformance
is
corrected.
The
facility
manager
of
the
facility
where
the
nonconformance
is
identified
ensures
that
an
NCR
is
initiated
and
that
corrective
action
is
taken
to
resolve
the
nonconformance.
WMP­
400,
Section
1.3.1,
guides
the
corrective
action
process.

NCRs
and
CARs
are
forwarded
to
the
SQAO.
The
SQAO
is
responsible
for
validating
and
tracking
project­
related
deficiencies
to
ensure
that
corrective
action
is
implemented
and
that
the
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corrective
action
resolves
the
nonconformance.
Project
personnel
notify
permittee
within
five
calendar
days
of
identification
of
any
nonadministrative
nonconformance
related
to
applicable
requirements
specified
in
the
WIPP
Hazardous
Waste
Facility
Permit
WAP,
which
are
first
identified
at
the
SPM's
signature
release
level.
Project
personnel
submit
the
NCR
to
permittee
within
30
calendar
days
of
identification
of
the
deficiency.
WMP­
400,
Section
1.3.1,
guides
the
corrective
action
process.
The
SQAO
ensures
dissemination
of
information
that
may
prevent
problems
or
help
improve
parallel
processes
in
other
waste
generator
or
project
activities
and
reevaluates
system
performance
after
corrective
actions
have
been
implemented.
The
facility
manager
provides
the
resources
necessary
to
accomplish
corrective
actions.

The
SQAO,
facility
managers,
and
FQAOs
are
jointly
responsible
for
identifying
the
following:

 
Trends
in
nonconformances
 
Root
causes
of
nonconformances
 
Specific,
measurable
corrective
actions
to
resolve
current
problems
and
prevent
recurrence
 
Personnel
responsible
for
implementing
corrective
actions
 
Schedules
for
completing
corrective
actions.

5.4
DOCUMENTS
Documents
that
specify
quality
requirements
or
establish
activities
affecting
quality
are
controlled
to
ensure
that
accurate
and
current
documents
are
used.
Document
control
ensures
that
documents
have
gone
through
the
designated
review
and
approval
process
and
are
distributed
to
the
appropriate
personnel.

Project
personnel
prepare
and
control
documents
supporting
the
quality
of
the
project
in
compliance
with
WMP­
400,
Section
1.4.1.
Document
control
coordinators
ensure
documents
are
developed
as
prescribed
by
current
procedures;
reviewed
for
adequacy,
correctness,
and
completeness;
approved;
revised;
and
distributed
to
the
appropriate
personnel.
Documents
developed
specifically
for
the
project
are
distributed
through
a
document
control
process.
These
documents
include:

 
Certification
plan
 
HNF­
2599
 
QAPD
procedures
matrix
 
Plans
and
procedures
implementing
the
TRU
waste
characterization,
certification,
packaging,
and
transportation
requirements.

5.5
RECORDS
A
QA
record
is
an
authenticated
record
that
furnishes
evidence
of
the
quality
of
items
and/
or
activities.
The
minimum
lifetime
and
nonpermanent
QA
project
records
are
identified
in
HNF­
2599.
QA
records
are
controlled
and
maintained
to
certify
compliance
with
requirements
and
to
reflect
completed
work.
QA
records
are
indexed,
classified,
controlled,
and
maintained
by
records
management
personnel
as
described
in
WMP­
400,
Section
1.5.1.
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5.6
WORK
PROCESSES
The
work
processes
and
items
supporting
and
affecting
project
quality
are
controlled
through
plans
and
procedures
identified
in
this
certification
plan,
HNF­
2599,
and
the
QAPD
procedures
matrix.
Procedures
and
plans
are
developed,
reviewed,
approved,
revised,
and
distributed
in
accordance
with
WMP­
400,
Section
1.4.1;
WMP­
400,
Section
2.1.2,
"
TRU
Operating
Procedure
Preparation
and
Approval";
WMP­
400,
Section
2.1.3,
"
TRU
Administrative
Procedure
Preparation
and
Approval";
and
WMP­
400,
Section
2.1.6,
"
TRU
Analytical
Procedure
Process."
Project
technical
and
QA
personnel
comply
with
the
applicable
technical
standards
and
administrative
controls
described
in
procedures,
which
are
reviewed
and
approved
by
the
SPM
(
or
designee),
the
SQAO
(
or
designee),
and
cognizant
facility
manager
in
accordance
with
WMP­
400,
Section
2.1.2,
Section
2.1.3,
and
Section
2.1.6,
as
appropriate.
Facility
managers
ensure
personnel
perform
work
following
established
procedures.

The
procedures
identified
in
this
certification
plan
and
HNF­
2599
provide
the
following
information:

 
Organizational
and
individual
responsibilities
 
Training
and
qualification
requirements
 
Technical,
regulatory,
and
QA
requirements
 
Step­
by­
step
instructions
for
the
process
(
prepared
by
an
SME
of
the
cognizant
organization)
 
Equipment
specifications
 
Methods
and
criteria
for
ensuring
and
verifying
the
acceptability
of
equipment
and
materials
used
in
the
process
(
e.
g.,
calibration)
 
Prerequisites,
precautions,
process
parameters,
and
other
limiting
conditions
 
Products
of
the
process
 
Quantitative
and/
or
qualitative
criteria
for
determining
that
prescribed
process
activities
have
been
performed
satisfactorily
 
Records
generated
by
the
process
 
Package
and
design
control
of
equipment
and
materials.

The
SPM
and
facility
managers
ensure
that
project
activities
are
controlled
and
conducted
in
accordance
with
WMP­
400,
Section
2.1.1,
"
TRU
Process
Control,"
and
facility­
specific
procedures
that
describe
and
control
work
processes
applicable
to
TRU
waste
characterization,
certification,
packaging,
or
transportation.
The
TRU
Project
does
not
perform
design
activities
that
impact
EPA
Disposal
certification.
Inspection
and
testing
is
addressed
in
subsection
5.8.

Each
individual
performing
the
work
is
responsible
for
ensuring
that:

 
Work
processes
are
controlled
and
comply
with
established
criteria,
and
 
Reports
describing
work
activity
results
are
correct
and
free
of
grammatical
and
spelling
errors.

Facility
managers
are
responsible
for
ensuring
that
workers
have
the
correct
procedures,
materials,
and
training
to
perform
quality
work.
All
instructions
and
procedures
are
maintained
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current
with
a
documented
and
controlled
method
of
revision
(
see
subsection
5.4).
Instructions,
procedures,
and
drawings
are
readily
available
to
project
personnel
at
locations
requiring
their
use.

Fabrication,
installation,
and
inspection
processes
that
have
an
effect
upon
the
quality
of
items
or
services
important
to
safety
shall
be
controlled
by
process
procedures.
Special
processes
controlled
under
this
QA
plan
are
nondestructive
testing
(
NDA,
NDE,
and
VE),
helium
leak
testing,
and
limited
maintenance
of
the
TRUPACT­
II
and
associated
components.
These
processes
are
controlled
by
the
following
written
procedures:

 
WMP­
400,
Section
1.2.2,
"
Qualification
of
NDE,
NDA,
Visual
Examination,
Transportation,
and
Inspection
and
Test
Personnel"
 
WMP­
400,
Section
2.4.4,
"
TRU
Control
of
Measuring,
Testing,
and
Data
Collection
Equipment"
 
WRP1­
OP­
0521,
"
Receive
and
Load
TRUPACT­
II
Containers"
 
WRP1­
OP­
0522,
"
Assemble
and
Stretch
Wrap
TRUPACT­
II
Payload"
 
WRP1­
OP­
0524,
"
Helium
Leak
Test
of
the
TRUPACT­
II
Shipping
Container"
 
WRP1­
OP­
0729,
"
Visual
Examination"
 
WRP1­
OP­
0905,
Imaging
Passive/
Active
Neutron
Assay
Operation"
 
WRP1­
OP­
0906,
"
Gamma
Energy
Assay
Operations"
 
WRP1­
OP­
0907,
"
Gamma
Energy
Assay
Operations
Using
NDA2000"
 
WRP1­
OP­
0908,
"
Operation
of
the
Drum
Nondestructive
Examination
System"
 
WRP1­
OP­
1225,
"
Radiological
Support
of
TRUPACT­
II
Shipping
and
Receiving"
 
ZA­
948­
392,
"
NDA
Using
NDA
2000"
 
ZA­
948­
393,
"
NDA
Using
the
Room
172
ANTECH
Calorimeters"

5.7
PROCUREMENT
All
Hanford
site
TRU
Project
facilities
implement
procedures
to
ensure
procurement
of
items
and
services
important
to
safety
and
quality
meet
requirements
and
perform
as
intended.
Procurement
controls
are
also
applicable
to
equipment
and
services
that
directly
affect
testing,
sampling,
and
analytical
data
quality.
Project
personnel
adhere
to
procurement
and
recordkeeping
practices
established
in
written
procedures.
The
procurement
criteria
are
implemented
according
to
WMP­
400,
Section
2.3.1,
"
TRU
Procurement
Planning,"
and
the
procedures
specified
in
the
following
subsections.

5.7.1
Procurement
Document
Control
The
SPM
and
facility
managers
ensure
project
personnel
control
procurement
documents
in
accordance
with
WMP­
400,
Section
2.3.2,
"
TRU
Procurement
Document
Control."
Procurement
documents
supporting
waste
management
and
packaging
and
transportation
activities
must
include
required
specifications
and
acceptance
criteria.
Procurement
documents
are
reviewed
by
appropriate
organizations
and
engineering
disciplines
to
ensure
they
contain
adequate
scope
of
work,
technical
requirements,
supplier
QA
program
requirements,
and
provisions
for
acceptance.
The
procurement
document
control
system
is
also
defined
in
WMP­
400,
Section
2.3.2.
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5.7.2
Control
of
Purchased
Items
and
Services
The
SPM
and
facility
managers
ensure
project
personnel
control
items
and
services
purchased
(
including
supplier
evaluations
and
inspections)
in
accordance
with
WMP­
400,
Section
2.3.3,
"
TRU
Control
of
Purchased
Items
and
Services,"
and
WMP­
400,
Section
2.4.1,
"
TRU
Inspection
Control."
Documentary
evidence
that
items,
material,
and
equipment
conform
to
the
procurement
specifications
is
provided
before
installation
or
use
of
the
item,
material,
and
equipment
and
is
retained
in
accordance
with
WMP­
400,
Section
2.3.2.
Potential
suppliers
of
goods
and
services
to
the
TRU
Project
will
have
their
own
QA
program
or
will
comply
with
applicable
TRU
Project
requirements.

Measures
are
established
in
WMP­
400,
Section
2.1.4,
"
TRU
Handling
and
Storage,"
and
WMP­
400,
Section
2.4.1,
to
ensure
that
materials,
parts,
and
components
used
for
repair
work
for
maintenance
purposes
or
packaging
and
transportation
purposes
are
adequately
identified
to
preclude
the
use
of
incorrect
or
defective
items.
Also,
where
replacement
of
limited­
life
items
is
specified,
measures
are
established
to
preclude
use
of
items
whose
shelf
life
or
time
in
operation
has
expired
(
see
subsection
5.8
of
this
Certification
Plan).

5.7.3
Control
of
Subcontractors
Subsection
5.7.2
of
this
Certification
Plan
also
applies
to
subcontractors
who
perform
work
that
directly
affects
the
quality
of
characterization
and
certification
data.
WMP­
400,
Section
2.3.3,
describes
how
project
personnel
control
subcontractor
services.
Subcontractors
may
support
TRU
Project
activities
under
a
"
staff
augmentation"
role
or
for
procurement
of
products
and
services.
TRU
Project
staff
augmentation
subcontractors
operate
under
the
umbrella
of
the
TRU
Project
QA
program
and
are
subject
to
all
applicable
requirements
for
TRU
Project­
related
functions
they
perform.
All
subcontractors
who
support
the
TRU
Project
will
be
informed
of
the
need
to
perform
operations
in
compliance
with
TRU
Project
requirements.
Subcontractors
are
required
to
establish
procurement
controls
and
a
QA
program
to
ensure
that
purchased
materials,
equipment,
and
services
conform
to
the
TRU
Project
procurement
and
QA
program
documents.
The
controls
must
include
provisions,
as
appropriate,
for
source
evaluation
and
selection,
objective
evidence
of
quality
furnished
by
the
contractor
or
subcontractor,
inspection
at
the
contractor
or
subcontractor
source,
and
examination
of
products
on
delivery.
Subcontractors
are
subject
to
periodic
assessments
and
audits
at
intervals
consistent
with
the
importance,
complexity,
and
quantity
of
the
product
or
services
provided
to
ensure
compliance
with
procurement
requirements.
Subcontractor
personnel
must
meet
applicable
project
training
and
qualification
requirements.
Subcontractors
shall
submit
copies
of
all
project­
related,
qualityaffecting
documents
to
the
SPM.

5.8
INSPECTION
AND
TESTING
Equipment
is
tested,
inspected,
and
maintained
in
accordance
with
WMP­
400,
Section
2.4.1;
WMP­
400,
Section
2.4.2,
"
TRU
Test
Control";
and
WMP­
400,
Section
2.4.4,
"
TRU
Control
of
Measuring,
Testing,
and
Data
Collection
Equipment."
Status
tagging
based
on
inspections
and/
or
tests
done
in
accordance
with
WMP­
400,
Section
2.4.5,
"
TRU
Identification
and
Control
of
Items."
Project
personnel
identify
and
control
items
(
e.
g.,
items
with
limited
shelf
or
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operating
lives,
materials,
equipment,
samples)
and
ensure
that
only
correct
and
accepted
items
are
used
according
to
WMP­
400,
Section
2.4.1.
These
procedures
and
documents
address
planning,
parameters
for
evaluation,
techniques
to
be
used,
qualification
of
inspection
and
test
personnel,
hold
points,
documentation,
acceptance
criteria,
and
organizational
responsibilities.

Project
personnel
routinely
test
and
inspect
items
and
processes
and
control,
calibrate,
and
maintain
equipment
to
ensure
proper
operation
and
data
quality.
Procedures
identified
above
implement
an
inspection
program
that
establishes
criteria
for
inspection
of
activities
affecting
quality
by
or
for
the
organization
performing
the
activity,
and
to
verify
conformance
with
the
requirements
for
accomplishing
the
activity.
The
verification
is
performed
in
accordance
with
written
procedures,
instructions,
or
drawings.
Personnel
performing
the
inspections
are
independent
from
the
individuals
performing
the
activity
being
inspected.
Equipment
modifications,
repairs,
and
replacement
are
inspected
in
accordance
with
the
original
design
and
inspection
requirements
unless
an
approved
alternative
exists.
The
inspection
program
also
provides
for
identification
and
documentation
of
deficiencies
discovered
during
the
inspection.
Measures
are
established
to
indicate,
by
the
use
of
markings,
tags,
stamps,
labels,
routing
cards,
or
other
suitable
means,
the
status
of
inspections
and
tests
performed.
These
measures
provide
for
the
identification
of
items
that
have
satisfactorily
passed
required
inspections
and
tests,
where
necessary,
to
preclude
inadvertent
bypassing
of
the
inspections
and
tests.

Measuring
and
test
equipment
with
the
necessary
range
and
accuracy
is
provided
to
qualified
personnel
for
the
inspection,
test,
and
acceptance
of
material,
parts,
components,
and
systems.
Equipment
accuracy
is
ensured
by
periodic
calibration
that
is
traceable
to
national
standards
or
a
documented
equivalent
basis
for
calibration.

The
test
control
program
is
established
for
items
and
services
important
to
safety.
No
testing
requiring
a
test
control
program
relative
to
waste
payload
containers
or
the
TRUPACT
II
will
be
performed
under
this
program.
All
TRUPACT­
II
repair
parts
that
may
be
replaced
by
the
operator
are
supplied
by
the
permittee
or
a
designated
contractor
and
are
tested,
inspected,
accepted,
and
tagged
in
accordance
with
the
permittee
DOE/
WIPP­
02­
3183
and
DOE/
WIPP­
02­
3184
manuals
before
delivery
to
the
user.
Leak
testing
is
a
special
process
discussed
in
subsection
5.6.

Specific
measures
to
control
packaging,
shipping,
storage,
preservation,
handling
of
components,
material,
and
packaging
to
prevent
damage,
loss,
deterioration,
or
substitution
are
established
in
the
following
procedures:

 
WRP1­
OP­
0521
 
WRP1­
OP­
0522
 
WRP1­
OP­
0524
 
WMP­
400,
Sections
2.1.5,
7.1.5,
7.1.7,
and
7.1.8.
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These
procedures
address
the
following
requirements:

 
Transport
cask
handling
and
operation
shall
conform
to
written
handling
and
operating
procedures
for
each
licensed.
 
Before
shipment
of
a
transport
cask,
conditions
of
the
NRC's
certificate
of
compliance
(
e.
g.,
specifications,
tests,
inspections)
shall
be
satisfied.
Required
shipping
papers
shall
be
prepared
and
shall
accompany
the
shipment.
 
Established
safety
restrictions
concerning
handling,
storage,
and
shipping
shall
be
included
in
the
handling
and
operating
procedures
for
transport
casks.

5.9
ASSESSMENT
REQUIREMENTS
The
Hanford
site
participates
in
an
assessments
program
to
ensure
that
the
project
is
in
compliance
with
applicable
requirements.
Management
assessments
are
conducted
by
Hanford
site
project
management
and
independent
assessments
by
site
personnel
independent
of
the
project.
Permittee
and
external
regulatory
agencies
also
conduct
assessments
of
the
TRU
Project.
The
SQAO
tracks
deficiencies
identified
during
assessments;
identifies
corrective
actions
to
resolve
deficiencies
according
to
WMP­
400,
Sections
1.3.1,
1.3.2,
and
1.3.3;
and
ensures
the
resolutions
are
reported
to
the
SPM,
RL,
and
permittee
as
described
in
subsection
5.3
of
this
Certification
Plan.

5.9.1
Management
Assessments
Project
managers
periodically
assess
the
performance
of
their
organization
to
determine
the
effectiveness
of
QA
program
provisions
that
enable
the
organization
to
comply
with
requirements
of
the
WAP,
QAPD,
CH­
WAC,
and
CH­
TRAMPAC,
and
applicable
procedures
and
documents.
Managers
evaluate
QA
program
effectiveness
by
focusing
on
the
identification
and
resolution
of
both
systemic
and
management
issues
and
problems,
and
identifying
strengths
and
weaknesses
to
facilitate
actions
to
improve
quality
efficiency
and
cost­
effectiveness.
The
management
assessment
includes
an
introspective
evaluation
to
determine
whether
the
entire
integrated
management
system
effectively
focuses
on
meeting
strategic
goals.
Management
assessments
are
conducted
as
described
in
WMP­
400,
Section
3.1.1,
"
TRU
Management
Assessment."
Project
managers
are
responsible
for
the
conduct
of
these
assessments
and
report
at
least
annually
on
relevant
findings.

5.9.2
Independent
Assessments
Documented
independent
assessments,
also
referred
to
as
audits
and
surveillances,
are
used
to
measure
item
service
and
quality,
process
adequacy
and
effectiveness,
and
to
promote
improvement.
Independent
assessments
are
conducted
in
accordance
with
WMP­
400,
Section
3.2.1,
"
TRU
Independent
Assessments."
Project
personnel
and
facilities
are
subject
to
periodic
independent
assessments
performed
by
teams
assembled
by
the
SQAO.
The
SQAO
ensures
that
characterization
facilities
and
analytical
laboratories
are
assessed
and
determines
whether
the
independent
assessment
is
an
audit
or
process
surveillance
(
see
below).
In
addition,
FQAOs
may
perform
independent
assessments
(
audits
or
surveillances)
of
project
activities
at
their
facilities.
Audit
teams
include
one
or
more
qualified
auditors,
one
of
whom
must
be
a
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certified
lead
auditor.
Audit
and
surveillance
personnel
qualifications
are
addressed
in
WMP­
400,
Sections
1.2.1
and
Section
1.2.3,
"
Certification
of
Audit
Personnel,"
and
are
in
accordance
with
the
QAPD.

The
independent
assessment
team
is
made
up
of
a
team
leader
appointed
by
the
SQAO
and
team
members
and
technical
specialists
selected
by
the
team
leader
in
conjunction
with
the
SQAO.
The
team
leader
provides
indoctrination
and
supervision
of
the
team,
organizes
and
directs
the
assessment,
establishes
the
scope
of
the
assessment,
prepares
a
plan
for
conducting
the
assessment,
and
prepares
and
issues
an
assessment
report
to
the
management
of
the
assessed
organization
and
any
affected
organizations.
The
assessment
team
members
and
technical
specialists
prepare
the
assessment
checklist,
conduct
the
assessment,
brief
the
management
of
the
assessed
organization
on
a
daily
basis,
and
prepare
a
draft
report
for
presentation
at
the
exit
conference
for
the
assessment.
Assessments
are
performed
in
accordance
with
WMP­
400,
Sections
3.2.1
and
3.2.2.

5.9.3
Audits
Facilities
participating
in
the
project
are
subject
to
permittee
audits.
A
permittee
audit
of
the
project
is
conducted
before
waste
is
shipped
to
WIPP
and
annually
thereafter.
These
audits
are
the
responsibility
of
the
permittee
QA
manager,
who
coordinates
these
audits
through
the
SPM
and
SQAO.

The
TRU
Project
also
participates
in
an
internal
audits
and
surveillance
program.
The
SQAO
ensures
that
all
conditions
adverse
to
quality
are
resolved
and
that
appropriate
corrective
actions
are
implemented
in
a
timely
manner.
The
SQAO
develops
a
schedule,
in
association
with
project
facility
managers,
which
details
follow­
up
activities
and
final
resolution
of
all
corrective
actions.
The
SQAO
tracks
corrective
actions
to
completion
and
monitors
the
status
of
the
corrective
actions
to
ensure
timely
closure
of
deficient
conditions.

5.9.4
Surveillances
The
surveillance
program
is
conducted
primarily
to
monitor
work
in
progress
and
to
follow
up
on
corrective
actions.
Surveillance
results
are
reported
and
monitored
similar
to
other
assessment
activities.
Surveillances
are
performed
in
accordance
with
WMP­
400,
Section
3.2.2,
"
TRU
Surveillance
Program."
HNF­
2600,
REV
15
Page
202
of
281
5/
11/
2005
HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
5.9.5
Reports
to
Management
The
SQAO
provides
the
QA
interface
between
facilities
and
the
SPM.
The
SQAO
oversees
the
NCR/
CAR
process
for
project­
related
deficiencies
and
coordinates
with
facility
managers
to
track
nonconformances
and
verify
corrective
action
completion
according
to
WMP­
400,
Sections
1.3.2
and
1.3.3.
Facility
QA
officers
(
FQAOs)
report
the
results
of
their
independent
assessments
to
the
SQAO,
and
together
they
track
assessment
results
and
corrective
actions.
The
SQAO
reports
these
independent
assessment
results
to
the
SPM
in
accordance
with
WMP­
400,
Section
3.1.2,
"
Quality
Assurance
Reports
to
Management."
Also,
the
SQAO
prepares
and
transmits
a
semiannual
QA
report
to
the
SPM
and
the
DOE.
The
semiannual
QA
report
includes
the
following
information,
as
appropriate:

 
Any
HNF­
2599
changes
 
Identification
of
any
significant
QA/
QC
problems,
recommended
solutions,
and
corrective
actions
 
An
assessment
of
QC
data
collected
during
the
period,
including
the
frequency
of
repeated
analyses,
reasons
they
were
repeated,
and
corrective
actions
 
Discussions
of
whether
QAOs
have
been
met
and
any
resulting
impact
on
decision
making
 
Limitations
on
the
use
of
measurement
data
 
Status
of
PDP
sample
results
 
Results
of
audits,
assessments,
and
surveillances
conducted
during
the
period.

5.9.6
Performance
Demonstration
Program
(
PDP)

The
Hanford
Site
TRU
Project
facilities
participate
in
the
PDP
programs
as
summarized
in
DOE/
CAO­
95­
1076,
Performance
Demonstration
Program
Plan
of
Simulated
Headspace
Gasses,
DOE/
CBFO­
01­
1005,
Performance
Demonstration
Program
Plan
for
Nondestructive
Assay
of
Drummed
Waste
for
the
TRU
Waste
Characterization
Program
and
DOE/
CBFO­
01­
1006
and
Performance
Demonstration
Program
Plan
for
Nondestructive
Assay
of
Boxed
Waste
for
the
TRU
Waste
Characterization
Program.
PDP
samples
are
processed
according
to
the
facility
procedures
applicable
to
the
specific
testing
or
analytical
characterization
activity
being
assessed.

5.10
SAMPLE
CONTROL
REQUIREMENTS
Project
personnel
use
procedures
to
ensure
proper
documentation
and
tracking
of
sample
possession
from
the
time
of
collection/
identification,
through
handling,
preservation,
shipment,
transfer,
analysis,
storage,
and
final
disposition.
Sample
control
procedures
used
by
project
personnel
are
described
in
LO­
090­
450,
"
TRU
Project
Chain
of
Custody,
Storage,
Acceptance,
and
Disposal."
Project
personnel
ship
samples
in
compliance
with
DOT
regulations
and
project
QA
requirements.

5.11
SCIENTIFIC
INVESTIGATION
REQUIREMENTS
The
plans
and
procedures
developed
and
implemented
to
support
the
project
define,
control,
verify,
and
document
data
collection
activities
related
to
TRU
waste
management.
HNF­
2600,
REV
15
Page
203
of
281
5/
11/
2005
HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
5.12
SOFTWARE
REQUIREMENTS
Computer
software
and
hardware/
software
configurations
used
in
project
activities
are
developed,
documented,
verified,
validated,
and
tested
before
use
in
compliance
with
requirements
contained
in
the
QAPD,
HNF­
2599,
and
NQA­
2a,
Subpart
2.7,
"
Quality
Assurance
Requirements
of
Computer
Software
for
Nuclear
Facility
Applications."
WMP­
400,
Section
6.1.1,
describes
the
processes
for
computer
software
development,
validation,
and
verification.

6.0
REFERENCES
10
CFR
Part
71,
"
Packaging
and
Transportation
of
Radioactive
Material,"
Code
of
Federal
Regulations,
Washington,
D.
C.,
Office
of
the
Federal
Register
National
Archives
and
Records
Administration.

10
CFR
Part
830,
"
Nuclear
Safety
Management,"
Code
of
Federal
Regulations,
Washington,
D.
C.,
Office
of
the
Federal
Register
National
Archives
and
Records
Administration.

10
CFR
Part
835,
"
Occupational
Radiation
Protection,"
Code
of
Federal
Regulations,
Washington,
D.
C.,
Office
of
the
Federal
Register
National
Archives
and
Records
Administration.

40
CFR
Part
191,
"
Environmental
Radiation
Protection
Standards
for
the
Management
and
Disposal
of
Spent
Nuclear
Fuel,
High­
Level
and
Transuranic
Radioactive
Wastes,"
Code
of
Federal
Regulations,
Washington,
D.
C.,
Office
of
the
Federal
Register
National
Archives
and
Records
Administration.

40
CFR
Part
194,
"
Criteria
for
the
Certification
and
Re­
Certification
of
the
Waste
Isolation
Pilot
Plant's
Compliance
with
the
40
CFR
Part
191
`
Disposal
Regulations',"
Code
of
Federal
Regulations,
Washington,
D.
C.,
Office
of
the
Federal
Register
National
Archives
and
Records
Administration.

40
CFR
Part
261,
"
Identification
and
Listing
of
Hazardous
Waste,"
Code
of
Federal
Regulations,
Washington,
D.
C.,
Office
of
the
Federal
Register
National
Archives
and
Records
Administration.

40
CFR
Part
262,
"
Standards
Applicable
to
Generators
of
Hazardous
Wastes,"
Code
of
Federal
Regulations,
Washington,
D.
C.,
Office
of
the
Federal
Register
National
Archives
and
Records
Administration.

40
CFR
Part
264,
"
Standards
for
Owners
and
Operators
of
Hazardous
Waste
Treatment,
Storage,
and
Disposal
Facilities,"
Code
of
Federal
Regulations,
Washington
D.
C.,
Office
of
the
Federal
Register
National
Archives
and
Records
Administration.

40
CFR
Part
268,
"
Land
Disposal
Restrictions,"
Code
of
Federal
Regulations,
Washington,
D.
C.,
Office
of
the
Federal
Register
National
Archives
and
Records
Administration.
HNF­
2600,
REV
15
Page
204
of
281
5/
11/
2005
HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
49
CFR
Part
172,
"
Hazardous
Materials
Table,
Special
Provisions,
Hazardous
Materials
Communications,
Emergency
Response
Information,
and
Training
Requirements,"
Code
of
Federal
Regulations,
Washington,
D.
C.,
Office
of
the
Federal
Register
National
Archives
and
Records
Administration.

49
CFR
Part
173,
"
Shippers­
General
Requirements
for
Shipments
and
Packagings,"
Code
of
Federal
Regulations,
Washington,
D.
C.,
Office
of
the
Federal
Register
National
Archives
and
Records
Administration.

ANSI/
AIM
BC1­
1995,
Uniform
Symbology
Specification
 
Code
39.
American
National
Standards
Institute,
Inc.,
1430
Broadway,
New
York,
NY
10018.

ASME
NQA­
1,
Quality
Assurance
Program
Requirements
for
Nuclear
Facilities,
1989
Edition,
New
York,
New
York,
American
Society
of
Mechanical
Engineers.

ASME
NQA­
2a­
1990,
Part
2.7,
Addenda
to
NQA­
2,
Quality
Assurance
Program
Requirements
of
Computer
Software
for
Nuclear
Facility
Applications,
New
York,
New
York,
American
Society
of
Mechanical
Engineers.

ASTM
C
1030­
95,
"
Determination
of
Plutonium
Isotopic
Composition
by
Gamma­
Ray
Spectrometry,"
American
Society
for
Testing
and
Materials,
Washington
D.
C.

DOE/
CAO­
2056,
40
CFR
191,
Compliance
Certification
Application,
Carlsbad
Field
Office,
Carlsbad,
New
Mexico,
U.
S.
Department
of
Energy.

DOE­
RL­
96­
57,
Test
and
Evaluation
Document
for
the
U.
S.
Department
of
Transportation
Specification
7A,
Type
A
Packaging,
U.
S.
Department
of
Energy.

Carlsbad
Field
Office
Interim
Guidance
on
Ensuring
that
Waste
Qualifies
for
Disposal
at
the
Waste
Isolation
Pilot
Plant,
,
Carlsbad
Field
Office,
Carlsbad,
New
Mexico,
U.
S.
Department
of
Energy.

DOE/
WIPP­
01­
3194,
CH­
TRU
Waste
Content
Codes
(
CH­
TRUCON)

DOE/
WIPP­
02­
3183,
Contact­
Handled
Packaging
Program
Guidance
DOE/
WIPP­
02­
3184,
Contact­
Handled
Packaging
Operations
Manual
DOE/
WIPP­
02­
3185,
Contact­
Handled
Maintenance
Manual
DOE/
CBFO­
94­
1012,
U.
S.
Department
of
Energy­
Carlsbad
Field
Office
Quality
Assurance
Program
Document,
,
Carlsbad
Field
Office,
Carlsbad,
New
Mexico,
U.
S.
Department
of
Energy.

DOE/
WIPP­
02­
3122,
Contact­
Handled
Transuranic
Waste
Acceptance
Criteria
for
the
Waste
Isolation
Pilot
Plant.
HNF­
2600,
REV
15
Page
205
of
281
5/
11/
2005
HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
DOE
O
435.1,
1999,
Radioactive
Waste
Management,
Washington,
D.
C.,
U.
S.
Department
of
Energy.

EPA­
600/
2­
80­
076,
A
Method
for
Determining
the
Compatibility
of
Hazardous
Wastes,
Washington
D.
C.,
U.
S.
Environmental
Protection
Agency.

SW­
846,
Test
Methods
for
Evaluating
Solid
Waste,
Physical/
Chemical
Methods,
Third
Edition,
Final
Update
I
and
Final
Update
II
and
III,
Office
Solid
Waste
and
Emergency
Response,
Washington,
D.
C.,
U.
S.
Environmental
Protection
Agency.

HNF­
2599,
Hanford
Site
Transuranic
Waste
Characterization
Quality
Assurance
Project
Plan.

HNF­
2601,
Hanford
Site
Transuranic
Waste
Project
Quality
Assurance
Program
Document
Procedures
Matrix.

Specifications,
Tolerances,
and
Other
Technical
Requirements
for
Weighing
and
Measuring
Devices,
Handbook
44,
Boulder,
Colorado,
U.
S.
Department
of
Commerce,
National
Institute
of
Standards
and
Technology.

Safety
Analysis
Report
for
the
TRUPACT­
II
Shipping
Package,
NRC
Docket
No.
71­
9218,
,
Office
of
Regulatory
Procedures,
Washington,
D.
C.,
U.
S.
Nuclear
Regulatory
Commission.

Waste
Isolation
Pilot
Plant
Land
Withdrawal
Act,
Public
Law
102­
579.

Waste
Isolation
Pilot
Plant
Hazardous
Waste
Facility
Permit,
NM4890139088­
TSDF,
Attachment
B,
including
B1
through
B6,
Santa
Fe,
New
Mexico,
New
Mexico
Environment
Department.

DOE/
WIPP­
95­
2065,
Waste
Isolation
Pilot
Plant
Safety
Analysis
Report,
Carlsbad,
New
Mexico,
Westinghouse
Electric
Corporation.

Contact­
handled
Transuranic
Waste
Authorized
Methods
for
Payload
Control
(
CH­
TRAMPAC),
Washington
D.
C.,
Office
of
Regulatory
Procedures,
U.
S.
Nuclear
Regulatory
Commission
CH_
TRU
Payload
Appendices,
Washington
D.
C.,
Office
of
Regulatory
Procedures,
U.
S.
Nuclear
Regulatory
Commission.

U.
S.
Nuclear
Regulatory
Commission.
Certificate
of
Compliance.
NRC
Docket
No.
71­
9218,
Washington,
D.
C.
Office
of
Regulatory
Procedures,
U.
S.
Nuclear
Regulatory
Commission.
(
http://
www.
wipp.
ws/
library/
t2sar/
cofc/
trucert.
pdf)
HNF­
2600,
REV
15
Page
206
of
281
5/
11/
2005
HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
APPENDIX
A
SUMMARY
OF
CH
TRU
WASTE
ACCEPTANCE
CRITERIA,

REQUIREMENTS,
AND
COMPLIANCE
AND
VERIFICATION
DOCUMENTS
AND
PROCEDURES
HNF­
2600,
REV
15
Page
207
of
281
5/
11/
2005
HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
CH­
WAC
&
Cert.

Plan
Sect.
CH­
TRAMPAC
(&
Cert.
Plan
Sect.,
if
app)
Criteria
Requirements
Compliance
and
Verification
Procedures
Container
Properties
Criteria
and
Requirements
3.2.1
2.1,
2.9
(
4.3.1)
Payload
Container
description
 
DOT
7A
Type
A
55­
gal.
drums,

pipe
overpacks,
SWBs,
and
TDOPs
(
including
dunnage)

 
Maximum
number
of
containers
and
authorized
packaging
configurations
shown
in
Table
3­
2
TRU
Waste
Transportation
Certification
and
Logistics
(
WMP­
400,
Section
2.1.5)

TRU
Procurement
Document
Control
(
WMP­
400,
Section
2.3.2)

TRU
Control
of
Purchased
Items
and
Services
(
WMP­
400,
Section
2.3.3)

Transuranic
Waste
Sample
and
Waste
Container
Management
Activities
(
WMP­
400,
Section
7.1.7)

Transuranic
Waste
Certification
(
WMP­
400,
Section
7.1.8)

Receive
and
Load
TRUPACT
Containers
(
WRP1­
OP­
0521)

3.2.2
2.3
(
4.3.3)
Weight
limits
and
center
of
gravity
 
 
1000
lbs/
55­
gal.
drum
 
 
certified
weight.
Limits
for
Type
A
equivalent
drums
 
 
4000
lbs/
SWB
 
 
6,700
lbs/
TDOP
 
 
TRUPACT­
II
configuration
limits
shown
in
Table
3­
1
TRU
Waste
Transportation
Certification
and
Logistics
(
WMP­
400,
Section
2.1.5)
Transuranic
Waste
Certification
(
WMP­
400,
Section
7.1.8)

3.2.3
2.1,
2.9
(
4.3.3)
Container
assembly
 
Fourteen
55­
gal.
drums
 
14
POCs
(
std.,
S100
&
S200
 
2
SWBs
(
including
one
bin)

 
2
SWBs
(
including
four
55­
gal.

drums)

 
1
TDOP
all
configurations
TRU
Waste
Transportation
Certification
and
Logistics
(
WMP­
400,
Section
2.1.5)

3.2.4
NA
Removable
surface
contamination
 
 
20
disintegrations
per
minute
(
dpm)/
100
cm2
alpha
 
 
200
dpm/
100
cm2
beta/
gamma
TRU
Waste
Transportation
Certification
and
Logistics
(
WMP­
400,
Section
2.1.5)
Transuranic
Waste
Certification
(
WMP­
400,
Section
7.1.8)

Radiological
Support
of
TRUPACT­
II
Shipping
and
Receiving
(
WRP1­
OP­

1225)

3.2.5
2.4
(
4.3.4)
Container
identification
/
labeling/

marking
 
Bar
code
with
unique
CIN
and
site
identification
 
Empty
 
Dunnage
TRU
Waste
Transportation
Certification
and
Logistics
(
WMP­
400,
Section
2.1.5)
HNF­
2600,
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208
of
281
5/
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2005
HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
CH­
WAC
&
Cert.

Plan
Sect.
CH­
TRAMPAC
(&
Cert.
Plan
Sect.,
if
app)
Criteria
Requirements
Compliance
and
Verification
Procedures
2.2
(
4.3.2)
Dunnage
 
Empty
55­
gal.
drums
 
Empty
SWBs
TRU
Waste
Transportation
Certification
and
Logistics
(
WMP­
400,
Section
2.1.5)
Receive
and
Load
TRUPACT
Containers
(
WRP1­
OP­
0521)

Assemble
and
Stretch
Wrap
TRUPACT
Payload
(
WRP1­
OP­
0522)

3.2.7
2.5
(
4.3.5)
Filter
vents
 
Payload
containers
vented
with
filters
that
meet
WAP
and
TRAMPAC
or
CH­
TRAMPAC
specifications
CH­
WAC
TRU
Waste
Transportation
Certification
and
Logistics
(
WMP­
400,
Section
2.1.5)

TRU
Control
of
Purchased
Items
and
Services
(
WMP­
400,
Section
2.3.3)

Transuranic
Waste
Certification
(
WMP­
400,
Section
7.1.8)

Headspace
Gas
Samples
of
TRU
Waste
Containers
(
TRU­
OP­
001)

Move
Containers
Throughout
WRAP
Facility
(
WRP1­
OP­
0503)

Assemble
and
Stretch
Wrap
TRUPACT
Payload
(
WRP1­
OP­
0522)

Physical
Properties
Criteria
and
Requirements
2.6
(
4.3.6)
Liquids
 
<
1
in.
(
2.5
cm)
in
the
bottom
of
any
container
 
<
1
volume
percent
in
any
payload
container
3.4.1
2.7
4.3.7
Sharp
or
Heavy
Objects
 
Sharp
or
heavy
objects
shall
be
blocked
or
braced
TRU
Waste
Transportation
Certification
and
Logistics
(
WMP­
400,
Section
2.1.5)
Transuranic
Waste
Repackaging,
Visual
Examination,
and
Sampling
(
WMP­

400,
Section
7.1.3)

Sampling
Design
and
Data
Analysis
for
RCRA
Characterization
and
Visual
Examination
of
Transuranic
Waste
(
WMP­
400,
Section
7.1.4)

Transuranic
Waste
Certification
(
WMP­
400,
Section
7.1.8)

AK
Documentation
Management
(
WMP­
400,
Section
7.1.9)

TRU
Waste
Visual
Exam
Technique
(
WMP­
400,
Section
7.1.10)

TRU
RWM
Glovebox
Automatic
Mode
Operations
(
WRP1­
OP­
0722)

TRU
Sorting
Glovebox
Operation
(
WRP1­
OP­
0725)

TRU
Loadout
Glovebox
Operation
(
WRP1­
OP­
0726)

Operation
of
the
Drum
Nondestructive
Examination
System
(
WRP1­
OP­

0908)

Pipe­
and­
Go
Operations
(
ZO­
160­
080)

Pu/
Al
Alloys
Operations
(
ZO­
160­
081)
(
Inactive)

Load
Standard
Waste
Box
(
SWB)
Storage
Containers
With
TRU
Waste
(
ZO­
170­
044)

Visual
Examination
Technique
for
PFP
Debris
Waste
(
ZO­
170­
057)

3.4.2
2.8
(
4.3.8)
Sealed
containers
 
Sealed
containers
>
4
L
prohibited
(
except
for
waste
material
Type
II.
2
packaged
in
a
metal
container)
TRU
Waste
Transportation
Certification
and
Logistics
(
WMP­
400,
Section
2.1.5)
Transuranic
Waste
Repackaging,
Visual
Examination,
and
Sampling
(
WMP­

400,
Section
7.1.3)
HNF­
2600,
REV
15
Page
209
of
281
5/
11/
2005
HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
CH­
WAC
&
Cert.

Plan
Sect.
CH­
TRAMPAC
(&
Cert.
Plan
Sect.,
if
app)
Criteria
Requirements
Compliance
and
Verification
Procedures
Sampling
Design
and
Data
Analysis
for
RCRA
Characterization
and
Visual
Examination
of
Transuranic
Waste
(
WMP­
400,
Section
7.1.4)

Transuranic
Waste
Certification
(
WMP­
400,
Section
7.1.8)

AK
Documentation
Management
(
WMP­
400,
Section
7.1.9)

TRU
Waste
Visual
Exam
Technique
(
WMP­
400,
Section
7.1.10)

TRU
RWM
Glovebox
Automatic
Mode
Operations
(
WRP1­
OP­
0722)

TRU
Sorting
Glovebox
Operation
(
WRP1­
OP­
0725)

TRU
Loadout
Glovebox
Operation
(
WRP1­
OP­
0726)

Operation
of
the
Drum
Nondestructive
Examination
System
(
WRP1­
OP­

0908)

Pipe­
and­
Go
Operations
(
ZO­
160­
080)

Pu/
Al
Alloys
Operations
(
ZO­
160­
081)
(
Inactive)

Load
Standard
Waste
Box
(
SWB)
Storage
Containers
With
TRU
Waste
(
ZO­
170­
044)

Visual
Examination
Technique
for
PFP
Debris
Waste
(
ZO­
170­
057)
HNF­
2600,
REV
15
Page
210
of
281
5/
11/
2005
HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
CH­
WAC
&
Cert.

Plan
Sect.
CH­
TRAMPAC
(&
Cert.
Plan
Sect.,
if
app)
Criteria
Requirements
Compliance
and
Verification
Procedures
Radiological
Properties
Criteria
and
Requirements
3.3.1
3.1
(
4.4.1)
Radionuclide
Composition
/

Nuclear
criticality
 
Assay
measurements
 
Quantification
of
:
241Am,
238Pu,

239Pu,
240Pu,
242Pu,
233U,
234U,

238U,
90Sr,
and
137Cs
TRU
Waste
Transportation
Certification
and
Logistics
(
WMP­
400,
Section
2.1.5)
Transuranic
Waste
Certification
(
WMP­
400,
Section
7.1.8)

Operation
of
the
SuperHENC
Assay
System
(
TRU­
OP­
002)

Calculation
of
Assay
Results
(
WMP
350,
Section
2.2)

Data
Management
(
WMP­
350,
Section
2.3)

GEA
Energy
and
Efficiency
Setup
and
Baseline
Establishment
(
WMP­
350,

Section
2.5)

WRAP
NDA
Measurement
Control
Program
(
WMP­
350,
Section
2.8)

Performing
Calibration
Verifications
and
Confirmations
for
NDA
at
WRAP
(
WMP­
350,
Section
2.9)

GEA
Calibration
Using
NDA2000
(
WMP­
350,
Section
2.10)

Imaging
Passive/
Active
Neutron
Assay
Operation
(
WRP1­
OP­
0905)

Gamma
Energy
Assay
Operations
(
WRP1­
OP­
0906)

Gamma
Energy
Assay
Operations
Using
NDA2000
(
WRP1­
OP­
0907)

Data
Management
(
FSP­
PFP­
5­
8,
Section
16.2)

QC
Criteria
for
Residues
Project
NDA
Instruments
(
FSP­
PFP­
5­
8,
Section
16.3)
Calibration
Confirmation
for
Residues
Project
NDA
Instruments
(
FSP­
PFP­

5­
8,
Section
16.4)

Calculation
of
Assay
Results
(
ZA­
400­
302)

Energy
and
Efficiency
Setup
and
Baseline
Determination
Using
NDA
2000
(
ZA­
400­
303)

ANTECH
Calorimeter
Calibration
(
ZA­
400­
304)

3.3.3
3.1
(
4.4.1)
Fissile
material
quantity
(
239Pu
fissile
gram
equivalent
[
FGE])
 
 
200
g/
55­
gal.
drum
(
including
pipe
overpacks)

 
 
325
g/
SWB
or
TDOP
 
 
325
g/
TRUPACT­
II
 
 
2,800
g/
TRUPACT­
II
(
14
pipe
overpacks)
TRU
Waste
Transportation
Certification
and
Logistics
(
WMP­
400,
Section
2.1.5)
Transuranic
Waste
Certification
(
WMP­
400,
Section
7.1.8)

Operation
of
the
SuperHENC
Assay
System
(
TRU­
OP­
002)

Calculation
of
Assay
Results
(
WMP­
350,
Section
2.2)

Data
Management
(
WMP­
350,
Section
2.3)

GEA
Energy
and
Efficiency
Setup
and
Baseline
Establishment
(
WMP­
350,

Section
2.5)

WRAP
NDA
Measurement
Control
Program
(
WMP­
350,
Section
2.8)

Performing
Calibration
Verifications
and
Confirmations
for
NDA
at
WRAP
HNF­
2600,
REV
15
Page
211
of
281
5/
11/
2005
HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
CH­
WAC
&
Cert.

Plan
Sect.
CH­
TRAMPAC
(&
Cert.
Plan
Sect.,
if
app)
Criteria
Requirements
Compliance
and
Verification
Procedures
(
WMP­
350,
Section
2.9)

GEA
Calibration
Using
NDA2000
(
WMP­
350,
Section
2.10)

Imaging
Passive/
Active
Neutron
Assay
Operation
(
WRP1­
OP­
0905)

Gamma
Energy
Assay
Operations
(
WRP1­
OP­
0906)

Gamma
Energy
Assay
Operations
Using
NDA2000
(
WRP1­
OP­
0907)

Data
Management
(
FSP­
PFP­
5­
8,
Section
16.2)

QC
Criteria
for
Residues
Project
NDA
Instruments
(
FSP­
PFP­
5­
8,
Section
16.3)
Calibration
Confirmation
for
Residues
Project
NDA
Instruments
(
FSP­
PFP­

5­
8,
Section
16.4)

Calculation
of
Assay
Results
(
ZA­
400­
302)

Energy
and
Efficiency
Setup
and
Baseline
Determination
Using
NDA
2000
(
ZA­
400­
303)

ANTECH
Calorimeter
Calibration
(
ZA­
400­
304)

NDA
Using
NDA
2000
(
ZA­
948­
392)

NDA
Using
the
Room
172
ANTECH
Calorimeters
(
ZA­
948­
393)

Pipe­
N­
Go
Operations
(
ZO­
160­
080)

Pu/
Al
Alloys
Operations
(
ZO­
160­
081)
(
Inactive)

3.3.3
NA
TRU
alpha
activity
 
>
100
nCi
of
alpha­
emitting
TRU
isotopes
with
half­
lives
greater
than
20
years
per
gram
of
waste
matrix
TRU
Waste
Transportation
Certification
and
Logistics
(
WMP­
400,
Section
2.1.5)
Transuranic
Waste
Certification
(
WMP­
400,
Section
7.1.8)

Operation
of
the
SuperHENC
Assay
System
(
TRU­
OP­
002)

Calculation
of
Assay
Results
(
WMP­
350,
Section
2.2)

Data
Management
(
WMP­
350,
Section
2.3)

Imaging
Passive/
Active
Neutron
Assay
Operation
(
WRP1­
OP­
0905)

Gamma
Energy
Assay
Operations
(
WRP1­
OP­
0906)

Gamma
Energy
Assay
Operations
Using
NDA2000
(
WRP1­
OP­
0907)

Data
Management
(
FSP­
PFP­
5­
8,
Section
16.2)

Calculation
of
Assay
Results
(
ZA­
400­
302)

Energy
and
Efficiency
Setup
and
Baseline
Determination
Using
NDA
2000
(
ZA­
400­
303)

ANTECH
Calorimeter
Calibration
(
ZA­
400­
304)

NDA
Using
NDA
2000
(
ZA­
948­
392)

NDA
Using
the
Room
172
ANTECH
Calorimeters
(
ZA­
948­
393)
HNF­
2600,
REV
15
Page
212
of
281
5/
11/
2005
HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
CH­
WAC
&
Cert.

Plan
Sect.
CH­
TRAMPAC
(&
Cert.
Plan
Sect.,
if
app)
Criteria
Requirements
Compliance
and
Verification
Procedures
3.3.4
NA
239Pu
equivalent
activity
(
239Pu
equivalentcuries
[
PE­
Ci])
Untreated
Waste
 
 
80
PE­
Ci/
55­
gal.
Drum
 
 
130
PE­
Ci/
SWB
 
 
130
PE­
Ci/
drum
overpacked
in
TDOP
 
 
1800
std.
POC
 
 
1100
PE­
Ci/
55­
gal.
drum
overpacked
in
SWB
or
TDOP
or
85­
gal.
drum
Solidified/
Vitrified
Waste
 
 
1800
PE­
Ci/
55­
gal.
drum
(
including
a
drum
containing
a
pipe
component)
(
see
PE­
Ci
table
in
subsection
3.3.5.1
of
this
Certification
Plan)
TRU
Waste
Transportation
Certification
and
Logistics
(
WMP­
400,
Section
2.1.5)
Transuranic
Waste
Certification
(
WMP­
400,
Section
7.1.8)

Operation
of
the
SuperHENC
Assay
System
(
TRU­
OP­
002)

Calculation
of
Assay
Results
(
WMP­
350,
Section
2.2)

Data
Management
(
WMP­
350,
Section
2.3)

Imaging
Passive/
Active
Neutron
Assay
Operation
(
WRP1­
OP­
0905)

Gamma
Energy
Assay
Operations
(
WRP1­
OP­
0906)

Gamma
Energy
Assay
Operations
Using
NDA2000
(
WRP1­
OP­
0907)

Data
Management
(
FSP­
PFP­
5­
8,
Section
16.2)

Calculation
of
Assay
Results
(
ZA­
400­
302)

Energy
and
Efficiency
Setup
and
Baseline
Determination
Using
NDA
2000
(
ZA­
400­
303)

ANTECH
Calorimeter
Calibration
(
ZA­
400­
304)

NDA
Using
NDA
2000
(
ZA­
948­
392)

NDA
Using
the
Room
172
ANTECH
Calorimeters
(
ZA­
948­
393)

3.3.6
3.2
(
4.4.2)
Radiation
dose
rate
 
 
200
mrem/
hr
(
at
surface
for
payload
containers
and
TRUPACT­
II)

 
 
10
mrem/
hr
at
2
meters
(
TRUPACT­
II
only)
TRU
Waste
Transportation
Certification
and
Logistics
(
WMP­
400,
Section
2.1.5)
Transuranic
Waste
Repackaging
Visual
Examination
and
Sampling
(
WMP­

400,
Section
7.1.3)

Transuranic
Waste
Certification
(
WMP­
400,
Section
7.1.8)

Receive
and
Load
TRUPACT
Containers
(
WRP1­
OP­
0521)

Radiological
Support
of
TRUPACT­
II
Shipping
and
Receiving
(
WRP1­
OP­

1225)

Chemical
Properties
Criteria
and
Requirements
3.5.1
4.1
(
4.5.1)
Pyrophoric
materials
 
<
1
weight
percent
radionuclide
pyrophorics
 
No
nonradionuclide
pyrophorics
TRU
Waste
Transportation
Certification
and
Logistics
(
WMP­
400,
Section
2.1.5)
Transuranic
Waste
Certification
(
WMP­
400,
Section
7.1.8)

Acceptable
Knowledge
Documentation
Management
(
WMP­
400,
Section
7.1.9)

3.5.2
NA
Hazardous
wastes
 
Characterization
per
HNF­
2599
(
as
defined
in
WAP)

 
Limited
to
EPA
hazardous
waste
numbers
approved
by
WIPP­
WAP
TRU
Waste
Transportation
Certification
and
Logistics
(
WMP­
400,
Section
2.1.5)
Transuranic
Waste
Characterization
Data
Quality
Objectives
Reconciliation
and
Reporting
(
WMP­
400,
Section
7.1.1)
HNF­
2600,
REV
15
Page
213
of
281
5/
11/
2005
HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
CH­
WAC
&
Cert.

Plan
Sect.
CH­
TRAMPAC
(&
Cert.
Plan
Sect.,
if
app)
Criteria
Requirements
Compliance
and
Verification
Procedures
Transuranic
Waste
Repackaging,
Visual
Examination,
and
Sampling
(
WMP­

400,
Section
7.1.3)

Sampling
Design
and
Data
Analysis
for
RCRA
Characterization
and
Visual
Examination
of
Transuranic
Waste
(
WMP­
400,
Section
7.1.4)

Transuranic
Waste
Transportation
and
Disposal
Certification
(
WMP­
400,

Section
7.1.8)

Acceptable
Knowledge
Documentation
Management
(
WMP­
400,
Section
7.1.9)

Data
Management
for
Headspace
Gas
Sampling
and
Analytical
Results
(
WMP­
400,
Section
8.1.8)

ACE
Program
Implementation
and
Operation
of
Spreadsheet
Interface
(
WMP­
310,
Section
9.1)

Mercury
Analysis
by
Cold
Vapor
Atomic
Absorption
(
LA­
325­
104)

Acid
Digestion
of
Solid
and
Liquid
Samples
for
Graphite
Furnace
Atomic
Absorption
Analysis
(
GFAA)
(
LA­
505­
100)

Metal
Analysis
by
Graphite
Furnace
Atomic
Absorption
(
GFAA)
using
the
Perkin­
Elmer
5100
PC
(
LA­
505­
102)

Inductively
Coupled
Plasma
(
ICP)
Emission
Spectrometric
Method
for
the
Applied
Research
Laboratories
(
LA­
505­
151)

Acid
Digestion/
Dilution
of
Aqueous
Samples
and
Extracts
(
LA­
505­
158)

Acid
Digestion
of
Sediments,
Sludges,
and
Soils
for
Inductively
Coupled
Plasma
(
ICP)
and
Atomic
Absorption
(
AA)
Analysis
(
LA­
505­
159)

Inductively
Coupled
Plasma
(
ICP)
Emission
Spectrometric
Method
for
Jarrel
Ash
Type
61E
(
LA­
505­
161)

Determination
of
Trace
Elements
and
Radionuclides
by
Inductively
Coupled
Plasma­
Mass
Spectrometry
using
TJA
Poems
(
LA­
506­
101)

Determination
of
Volatile
Organic
Compounds
in
TRU/
Mixed
Waste
Container
Headspace
(
LA­
523­
410)

Determination
of
Total
Nonmethane
Organic
Compounds
in
TRU
Waste
Container
Headspace
(
LA­
523­
425)

Polychlorinated
Biphenyls
(
PCBs)
by
Volatile
Sample
Analysis
by
SSW­
846
(
LA­
523­
455)

Semivolatile
Sample
Analysis
by
SW­
846,
Method
8270B1
(
LA­
523­
456)

3.5.3
4.3
(
4.5.3)
Chemical
Composition
Chemicals
allowed
within
a
given
waste
material
type
so
a
conservative
bonding
TRU
Waste
Transportation
Certification
and
Logistics
(
WMP­
400,
Section
2.1.5)
HNF­
2600,
REV
15
Page
214
of
281
5/
11/
2005
HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
CH­
WAC
&
Cert.

Plan
Sect.
CH­
TRAMPAC
(&
Cert.
Plan
Sect.,
if
app)
Criteria
Requirements
Compliance
and
Verification
Procedures
G
value
can
be
established
Transuranic
Waste
Repackaging,
Visual
Examination,
and
Sampling
(
WMP­

400,
Section
7.1.3)

Transuranic
Waste
Certification
(
WMP­
400,
Section
7.1.8)

Acceptable
Knowledge
Documentation
Management
(
WMP­
400,
Section
7.1.9)

TRU
Waste
Visual
Examination
Technique
(
WMP­
400,
Section
7.1.10)

4.4
(
4.5.4)
Chemical
compatibility
All
chemicals
must
be
allowable
per
the
CH­
TRAMPAC
TRU
Waste
Transportation
Certification
and
Logistics
(
WMP­
400,
Section
2.1.5)
Transuranic
Waste
Repackaging,
Visual
Examination,
and
Sampling
(
WMP­

400,
Section
7.1.3)

Transuranic
Waste
Certification
(
WMP­
400,
Section
7.1.8)

Acceptable
Knowledge
Documentation
Management
(
WMP­
400,
Section
7.1.9)

3.5.4
4.2
(
4.5.2)
Explosives,

corrosives,

and
compressed
gases
 
No
explosives,
compressed
gases,

or
pressurized
containers
 
No
ignitable,
reactive,
or
corrosive
wastes
TRU
Waste
Transportation
Certification
and
Logistics
(
WMP­
400,
Section
2.1.5)
Transuranic
Waste
Repackaging,
Visual
Examination,
and
Sampling
(
WMP­

400,
Section
7.1.3)

Transuranic
Waste
Certification
(
WMP­
400,
Section
7.1.8)

Acceptable
Knowledge
Documentation
Management
(
WMP­
400,
Section
7.1.9)

TRU
Waste
Visual
Examination
Technique
(
WMP­
400,
Section
7.1.10)

TRU
RWM
Glovebox
Automatic
Mode
Operations
(
WRP1­
OP­
0722)

TRU
Sorting
Glovebox
Operation
(
WRP1­
OP­
0725)

TRU
Loadout
Glovebox
Operation
(
WRP1­
OP­
0726)

TRU
Waste
Certification
­
Operation
of
the
Drum
NDE
System
(
WRP1­
OP­

0908)

Pipe­
and­
Go
Operations
(
ZO­
160­
080)

Pu/
Al
Alloys
Operations
(
ZO­
160­
081)
(
Inactive)

Load
Standard
Waste
Box
(
SWB)
Storage
Containers
With
TRU
Waste
(
ZO­
170­
044)

Visual
Examination
Technique
for
PFP
Debris
Waste
(
Z0­
170­
057)

3.5.6
NA
PCB
concentration
 
<
50
ppm
TRU
Waste
Transportation
Certification
and
Logistics
(
WMP­
400,
Section
2.1.5)
Transuranic
Waste
Certification
(
WMP­
400,
Section
7.1.8)

Acceptable
Knowledge
Documentation
Management
(
WMP­
400,
Section
HNF­
2600,
REV
15
Page
215
of
281
5/
11/
2005
HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
CH­
WAC
&
Cert.

Plan
Sect.
CH­
TRAMPAC
(&
Cert.
Plan
Sect.,
if
app)
Criteria
Requirements
Compliance
and
Verification
Procedures
7.1.9)

Gas
Generation
Properties
Criteria
and
Requirements
3.3.7
5.0
(
4.6.2)
Decay
heat
Test
category
waste
 
 
Decay
heat
limit
for
the
authorized
shipping
category
 
 
40
W
per
TRUPACT­
II
TRU
Waste
Transportation
Certification
and
Logistics
(
WMP­
400,
Section
2.1.5)
Transuranic
Waste
Certification
(
WMP­
400,
Section
7.1.8)

Operation
of
the
SuperHENC
Assay
System
(
TRU­
OP­
002)

Calculation
of
Assay
Results
(
WMP­
350,
Section
2.2)

Data
Management
(
WMP­
350,
Section
2.3)

Imaging
Passive/
Active
Neutron
Assay
Operation
(
WRP1­
OP­
0905)

Gamma
Energy
Assay
Operations
(
WRP1­
OP­
0906)

Gamma
Energy
Assay
Operations
Using
NDA2000
(
WRP1­
OP­
0907)

Data
Management
(
FSP­
PFP­
5­
8,
Section
16.2)

Calculation
of
Assay
Results
(
ZA­
400­
302)

Energy
and
Efficiency
Setup
and
Baseline
Determination
Using
NDA
2000
(
ZA­
400­
303)

ANTECH
Calorimeter
Calibration
(
ZA­
400­
304)

NDA
Using
NDA
2000
(
ZA­
948­
392)

NDA
Using
the
Room
172
ANTECH
Calorimeters
(
ZA­
948­
393)

3.5.5
5.0
(
4.6.2)
Headspace
gas
VOC
concentration
 
Every
container
or
randomly
selected
containers
from
waste
streams
that
meet
the
conditions
for
reduced
headspace
gas
sampling
will
be
headspace
gas
sampled
per
HNF­
2599
as
defined
in
the
WAP
 
 
500
ppm
VOC
for
analytical
category
 
 
500
ppm
VOC
for
test
category
 
Hydrogen
methane
gas
sampler
per
Appendix
F.
TRU
Waste
Transportation
Certification
and
Logistics
(
WMP­
400,
Section
2.1.5)
Sampling
Design
and
Data
Analysis
for
RCRA
Characterization
and
Visual
Examination
of
Transuranic
Waste
(
WMP­
400,
Section
7.1.4)

Transuranic
Waste
Certification
(
WMP­
400,
Section
7.1.8)

Acceptable
Knowledge
Documentation
Management
(
WMP­
400,
Section
7.1.9)

Data
Management
for
Headspace
Gas
Sampling
and
Analytical
Results
(
WMP­
400,
Section
8.1.8)

Headspace
Gas
Samples
of
TRU
Waste
Containers
(
TRU­
OP­
001)

Determination
of
Volatile
Organic
Compounds
in
TRU/
Mixed
Waste
Container
Headspace
(
LA­
523­
410)

Determination
of
permanent
gases
in
TRU
waste
container
headspace
(
LA­

523­
426)

N/
A
5.3
Venting
and
 
 
Times
shown
in
CH­
TRUCON
TRU
Waste
Transportation
Certification
and
Logistics
(
WMP­
400,
Section
HNF­
2600,
REV
15
Page
216
of
281
5/
11/
2005
HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
CH­
WAC
&
Cert.

Plan
Sect.
CH­
TRAMPAC
(&
Cert.
Plan
Sect.,
if
app)
Criteria
Requirements
Compliance
and
Verification
Procedures
(
4.6.3)
aspiration
tables
 
Options
for
determining
aspiration
time
based
on
date
of
drum
closure
2.1.5)
Sampling
Design
and
Data
Analysis
for
RCRA
Characterization
and
Visual
Examination
of
Transuranic
Waste
(
WMP­
400,
Section
7.1.4)

Transuranic
Waste
Certification
(
WMP­
400,
Section
7.1.8)

N/
A
5.1
(
4.6.1)
Payload
shipping
category
 
Approved
content
codes
listed
in
CH­
TRUCON
tables
 
Assigned
shipping
category
per
WIPP
CH­
TRU
Payload
Engineer
 
Derived
shipping
category
decay
heat
limits
for
TRUPACT­
II
TRU
Waste
Transportation
Certification
and
Logistics
(
WMP­
400,
Section
2.1.5)
Transuranic
Waste
Repackaging,
Visual
Examination,
and
Sampling
(
WMP­

400,
Section
7.1.3)

Transuranic
Waste
Certification
(
WMP­
400,
Section
7.1.8)

Acceptable
Knowledge
Documentation
Management
(
WMP­
400,
Section
7.1.9)

TRU
Waste
Visual
Exam
Technique
(
WMP­
400,
Section
7.1.10)

Receive
and
Load
TRUPACT
Containers
(
WRP1­
OP­
0521)

TRU
RWM
Glovebox
Automatic
Mode
Operations
(
WRP1­
OP­
0722)

TRU
Sorting
Glovebox
Operation
(
WRP1­
OP­
0725)

TRU
Loadout
Glovebox
Operation
(
WRP1­
OP­
0726)

Operation
of
the
Drum
Nondestructive
Examination
System
(
WRP1­
OP­

0908)

Pipe­
and­
Go
Operations
(
ZO­
160­
080)

Pu/
Al
Alloys
Operations
(
ZO­
160­
081)
(
Inactive)

Load
Standard
Waste
Box
(
SWB)
Storage
Containers
With
TRU
Waste
(
ZO­
170­
044)

Visual
Examination
Technique
for
PFP
Debris
Waste
(
ZO­
170­
057)

N/
A
3.3
4.4.3
Activity
Limits
 
S100
POC
maximum
total
activity
TRU
Waste
Transportation
Certification
and
Logistics
(
WMP­
400,
Section
2.1.5)
Transuranic
Waste
Certification
(
WMP­
400,
Section
7.1.8)
HNF­
2600,
REV
15
Page
217
of
281
5/
11/
2005
HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
CH­
WAC
&
Cert.

Plan
Sect.
CH­
TRAMPAC
(&
Cert.
Plan
Sect.,
if
app)
Criteria
Requirements
Compliance
and
Verification
Procedures
Data
Packages
Criteria
and
Requirements
3.6.2
6.0
(
4.7)
Shipping
data
 
Payload
Container
Transportation
Certification
Document
 
Overpack
PCTCD
 
Payload
Assembly
Transportation
Certification
Document
(
analytical/
test)

 
Bill
of
ladingb
 
Land
disposal
restriction
notification
a
 
UHWMa
TRU
Waste
Transportation
Certification
and
Logistics
(
WMP­
400,
Section
2.1.5)
Receive
and
Load
TRUPACT
Containers
(
WRP1­
OP­
0521)

Radiological
Support
of
TRUPACT­
II
Shipping
and
Receiving
(
WRP1­
OP­

1225)
Determination
of
Permanent
Gases
in
TRU
Waste
Container
Headspace
(
LA­
523­
426)

a
Applies
to
mixed
wastes
only
(
a
one­
time
notice
per
waste
stream)

b
A
Uniform
Hazardous
Waste
Manifest
may
be
substituted
HNF­
2600,
REV
15
Page
218
of
281
5/
11/
2005
HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
APPENDIX
B­
1
PAYLOAD
CONTAINER
TRANSPORTATION
CERTIFICATION
DOCUMENT:
ANALYTICAL
PAYLOAD
SHIPPING
CATEGORY
HNF­
2600,
REV
15
Page
219
of
281
5/
11/
2005
HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
TRUPACT­
II
PAYLOAD
CONTAINER
TRANSPORTATION
CERTIFICATION
DOCUMENT
(
PCTCD)
(
Analytical
Category)
a
IDENTIFICATION
PARAMETERS
Container/
Barcode
ID#
Certification
Site
Shipping
Category
Content
Code
Direct
Load
Configurations

55­
Gallon
Drum

85­
Gallon
Drum

SWB

TDOP
Fixed
Configurations

6­
inch
Standard
Pipe
Overpack

12­
inch
Standard
Pipe
Overpack

S100
Pipe
Overpack

S200
Pipe
Overpack

SWB
with
Bin
(
Bin
Overpack)

Overpacked
Configurations

85­
Gallon
Drum
with
55­
Gallon
Drum
(
85­
Gallon
Drum
Overpack)


SWB
with
55­
Gallon
Drum(
s)
(
SWB
Overpack)


TDOP
with
55­
Gallon
Drum(
s)

TDOP
with
SWB
Overpack

TDOP
with
85­
Gallon
Drum
Overpack(
s)

TDOP
with
85­
Gallon
Drum(
s)


TDOP
with
SWB

TDOP
with
Bin
Overpack
CH­
TRAMPAC
TRANSPORTATION
PARAMETERS
Parameter
Initials
Filter(
s)
Identification
Residual
liquids
are
<
1%
of
payload
container
volume
Sharp/
heavy
objects
are
blocked/
braced/
suitably
packaged
Nonradioactive
pyrophorics
are
not
present
or
have
been
reacted
Radioactive
pyrophorics
are
<
1%
(
weight)
Explosives
are
not
present
Corrosives
are
not
present
Pressurized
containers
and
compressed
gases
are
not
present
Sealed
container
>
4
liters
are
not
present
(
except
for
Waste
Material
Type
II.
2)
Rigid
liner
(
if
present)
is
punctured/
vented
Flammable
VOCs
are
 
500
ppm
Surface
radiation
dose
rate
is
<
payload
container
limitb
1.
2.

3.
4.

5.
5.

7.
7.

9.
10.

MEASURED
PARAMETERS
Container
Parameter
Value
Error
Value
+
1x
Error
Value
+
2x
Error
Limit
Weight
(
lbs)
Decay
heat
(
watts)
Fissile
mass
(
FGE)
Curie
limits
(
Ci)
S200
Pipe
overpacks
only
Payload
container
meets
limits
specified
in
Section
3.3
of
THE
CH­
TRAMPAC
Yes/
No
HNF­
2600,
REV
15
Page
220
of
281
5/
11/
2005
HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
UNVENTED
WASTE
PARAMETERS
ONLY
Aspiration
Method

Option
1

Option
2a

Option
2b

Option
3
Aspiration
period
(
if
applicable)
days
Option
1
Container
closed
time
months
Aspiration
table
no.
(
if
applicable)
Options
2a,
2b,
or
3
Headspace
H2
concentration
mol%
Time
container
vented
days
I
certify
that
the
above
container
meets
all
the
requirements
for
shipment
as
stated
in
the
CH­
TRAMPAC.
The
container
is
approved
for

payload
assembly
or

overpacking.

/
Transportation
Certification
Official
(
print/
sign)
Date
aFollow
instructions
in
Section
6.2.1.1.
bLimits
are
not
applicable
if
container
is
to
be
overpacked.
HNF­
2600,
REV
15
Page
221
of
281
5/
11/
2005
HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
APPENDIX
B­
2
OVERPACK
PAYLOAD
CONTAINER
TRANSPORTATION
CERTIFICATION
DOCUMENT
(
OPCTCD)
HNF­
2600,
REV
15
Page
222
of
281
5/
11/
2005
HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
OVERPACK
PAYLOAD
CONTAINER
TRANSPORTATION
CERTIFICATION
DOCUMENT
(
OPCTCD)
a
IDENTIFICATION
PARAMETERS
Overpack
Container
ID#
Overpack
Container
Bar
Code
#
Governing
Payload
Shipping
Category
Numberb
Governing
Decay
Heat
Limitb
Governing
Hydrogen/
Flammable
Gas
Generation
Rate
Limitb
Overpack
Container
Type

85­
Gallon
Drum

SWB

TDOP
Overpacked
Container
Type(
s)

55­
Gallon
Drum(
s)

SWB

SWB
Overpack

85­
Gallon
Drum
Overpack(
s)

85­
Gallon
Drum
(
s)


Bin
Overpack
Weight
Limitc
(
lbs)
Fissile
Mass
Limitc
FGE
Certification
Site
Content
Code
CH­
TRAMPAC
TRANSPORTATION
PARAMETERS
Surface
Radiation
Dose
Rate
 
payload
container
limitc
Initials
Filter
Identification
1.
2.
3.
4.
5.
6.
7.
8.
9.
10.

OVERPACKED
CONTAINER
MEASURED
PARAMETERS
Overpacked
Container
ID
Number
Weight
(
lbs)
Error
(
lbs)
Decay
Heat
(
watts)
Error
(
watts)
Decay
Heat
Limits
(
watts)
Fissile
Mass
(
FGE)
2x
Error
(
FGE)
Hydrogen/
Flammable
Gas
Generation
Rate
(
mol/
s)
Flammability
Limitd
 
Weight
and
error
of
empty
overpack
payload
container
(
if
applicable)
Total
(
A)
Total
RMS*
Error
Total
+
RMS*
Error
HNF­
2600,
REV
15
Page
223
of
281
5/
11/
2005
HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
CERTIFICATION
OF
COMPLIANCE
Initials
Total
weight
+
weight
error
 
limitc
Total
fissile
mass
+
2x
fissile
mass
error
 
limitc
Decay
heat
+
decay
heat
error
 
decay
heat
limit
of
governing
payload
shipping
category
for
each
analytical
category
payload
containerb
Hydrogen/
flammable
gas
generation
rate
 
hydrogen/
flammable
gas
generation
rate
limit
of
governing
payload
shipping
category
for
each
test
category
payload
containerb
Flammability
Index
(
FI)
of
each
overpacked
container
meets
the
following
criteria:
0
 
FI
 
50,000d
*
Calculated
as
RSS
I
certify
that
the
above
overpack
container
meets
all
the
requirements
for
shipment
as
an
overpack
as
stated
in
the
CH­
TRAMPAC.
The
overpack
is
approved
for

payload
assembly
or

overpacking.

/
Transportation
Certification
Official
(
print/
sign)
Date
aFollow
instructions
in
Section
6.2.1.3
of
the
CH­
TRAMPAC.
bNot
applicable
if
mixing
shipping
categories
pursuant
to
Section
4.7.4.
cLimits
are
not
applicable
if
container
is
to
be
overpacked.
dApplicable
if
mixing
shipping
categories
pursuant
to
Section
4.7.4.
FI
is
determined
as
part
of
payload
assembly
(
Section
6.2.2
of
the
CH­
TRAMPAC).
HNF­
2600,
REV
15
Page
224
of
281
5/
11/
2005
HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
APPENDIX
B­
3
TRUPACT­
II
TEST
CATEGORY
PAYLOAD
CONTAINER
DATA
SHEET
HNF­
2600,
REV
15
Page
225
of
281
5/
11/
2005
HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
TRUPACT­
II
TEST
CATEGORY
PAYLAOD
CONTAINER
DATA
SHEET
(
Example)

SECTION
1
Identification
Parameters
Container
ID
No.
Container
Bar
Code
No.

Shipping
Category
Content
Code
Container
Type

55­
gal.
drum

SWB

TDOP

85­
gal
drum
Filter
Type
Certification
Site
Test
Category
Classification
Measurement
(
Waste
Types
I,
II,
or
III)
55­
Gal.
Drum
Testing
(
Complete
Sections
2,
3,
4,
and
6)
(
Complete
Sections
2,
3,
5,
and
6)


Decay
Heat
>
Analytical
Limit

Decay
Heat
>
Analytical
Limit

Flammable
VOC
Concentration
>
500
ppm

Fail
Measurement

Waste
Type
IV
SECTION
2
Methane
Concentration
Location
of
methane
measurement
Container
headspace/
inside
liner
Date
of
methane
measurement
Measured
methane
concentration
(
ppm)

Measured
methane
concentration
 
1,250
ppm
YES/
NO
HNF­
2600,
REV
15
Page
226
of
281
5/
11/
2005
HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
SECTION
3
Flammable
VOC
Concentration

No
flammable
VOCs
present

Maximum
concentration
of
flammable
VOCs
in
payload
container
headspace
 
500
ppm
(
from
process
knowledge)

Flammable
VOC
Headspace
Measured
Concentration
(
ppm)
Predicted
Innermost
Confinement
Layer
Concentration
(
ppm)
Acetone
Benzene
1­
Butanol
Chlorobenzene
Cyclohexane
1,1­
Dichloroethane
1,2­
Dichloroethane
1,1­
Dichloroethene
cis­
1,2­
Dichloroethene
Ethyl
benzene
Ethyl
ether
Methanol
Methyl
ethyl
ketone
Methyl
isobutyl
ketone
Toluene
1,2,4­
Trimethylbenzene
1,3,5­
Trimethylbenzene
m­
Xylene
o­
Xylene
p­
Xylene
Sum
of
flammable
VOCs
HNF­
2600,
REV
15
Page
227
of
281
5/
11/
2005
HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
SECTION
4
Measurement
1.
Decay
heat
plus
error
(
W)

Wattage
limit
for
TRUPACT­
II
design
pressure
limit
Decay
heat
plus
error
 
wattage
limit
for
TRUPACT­
II
Design
pressure
limit
YES/
NO
2.
Calculated
flammable
gas
generation
rate
(
FGGR)
(
mol/
sec)

3a.
Maximum
allowable
hydrogen
gas
generation
rate
of
container
or
controlling
shipping
category
(
mol/
sec)

Calculated
FGGR
 
maximum
allowable
hydrogen
gas
generation
rate
of
container
or
controlling
shipping
category
YES/
NO
3b.
Calculated
innermost
confinement
layer
flammable
gas
concentration
(
vol
%)

Mixture
lower
explosive
limit
(
MLEL)
(
vol
%)

Calculated
innermost
confinement
layer
flammable
gas
concentration
plus
sum
of
flammable
VOCs
(
innermost
confinement
layer
concentration)
(
vol
%)

Calculated
innermost
confinement
layer
flammable
gas
plus
flammable
VOCs
 
MLEL
YES/
NO
HNF­
2600,
REV
15
Page
228
of
281
5/
11/
2005
HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
SECTION
5
55­
Gallon
Drum
Testing
1.
Decay
heat
plus
error
(
W)

2.
Maximum
decay
heat
per
drum
and
per
TRUPACT­
II
(
W)

3a.
May
gas
generation
testing
be
performed
at
room
temperature?
YES/
NO
3b.
Total
measured
gas
release
rate
(
mol/
sec)

Maximum
allowable
total
gas
release
rate
(
mol/
sec)

Total
measured
gas
release
rate
 
maximum
allowable
gas
release
rate
limit
YES/
NO
4.
Measured
flammable
gas
generation
rate
(
FGGR)
(
mol/
sec)

5a.
Maximum
allowable
hydrogen
gas
generation
rate
(
mol/
sec)

Measured
FGGR
 
maximum
allowable
hydrogen
gas
generation
rate
YES/
NO
5b.
Calculated
innermost
confinement
layer
flammable
gas
concentration
(
vol
%)

Mixture
lower
explosive
limit
(
MLEL)
(
vol
%)

Calculated
innermost
confinement
layer
flammable
gas
concentration
plus
sum
of
flammable
VOCs
(
innermost
confinement
layer
concentration)
(
vol
%)

Calculated
innermost
confinement
layer
flammable
gas
plus
flammable
VOCs
 
MLEL
YES/
NO
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HANFORD
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TRANSURANIC
WASTE
CERTIFICATION
PLAN
SECTION
6
Measurement/
Testing
Certification
Does
payload
container
meet
test
category
criteria?
YES/
NO
/
(
Print
Name)
(
Sign
Name)
(
Date)
Transportation
Certification
Official
HNF­
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REV
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230
of
281
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2005
HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
APPENDIX
C
PAYLOAD
CONTAINER
TRANSPORTATION
CERTIFICATION
DOCUMENT:
TEST
PAYLOAD
SHIPPING
CATEGORY
HNF­
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HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
TRUPACT­
II
PAYLOAD
CONTAINER
TRANSPORTATION
CERTIFICATION
DOCUMENT
(
PCTCD)
(
Test
Category)
a
IDENTIFICATION
PARAMETERS
Container
ID
#
Container
Barcode
#
Certification
Site
Container
Designated
for
Controlled
Shipment?

Yes

No
Shipping
Category
Content
Code
Direct
Load
Configurations

55­
Gallon
Drum

85­
Gallon
Drum

100­
Gallon
Drum

SWB

TDOP
Fixed
Configurations

6­
inch
Standard
Pipe
Overpack

12­
inch
Standard
Pipe
Overpack

S100
Pipe
Overpack

S200
Pipe
Overpack

S300
Pipe
Overpack

SWB
with
Bin
(
Bin
Overpack)

Overpacked
Configurations

85­
Gallon
Drum
with
55­
Gallon
Drum
(
85­
Gallon
Drum
Overpack)


SWB
with
55­
Gallon
Drum(
s)
(
SWB
Overpack)


TDOP
with
55­
Gallon
Drum(
s)

TDOP
with
SWB
Overpack

TDOP
with
85­
Gallon
Drum
Overpack(
s)

TDOP
with
85­
Gallon
Drum(
s)


TDOP
with
SWB

TDOP
with
Bin
Overpack
CH­
TRAMPAC
TRANSPORTATION
PARAMETERS
Parameter
Initials
Filter(
s)
Identification
Residual
liquids
are
<
1%
of
payload
container
volume
Sharp/
heavy
objects
are
blocked/
braced/
suitably
packaged
Nonradioactive
pyrophorics
are
not
present
or
have
been
reacted
Radioactive
pyrophorics
are
<
1%
(
weight)
Explosives
are
not
present
Corrosives
are
not
present
Pressurized
containers
and
compressed
gases
are
not
present
Sealed
container
>
4
liters
are
not
present
(
except
for
Waste
Material
Type
II.
2)
Rigid
liner
(
if
present)
is
punctured/
vented
Surface
radiation
dose
rate
is
<
payload
container
limitb
1.
2.

3.
4.

5.
6.

7.
8.

9.
10.

MEASURED
PARAMETERS
Container
Parameter
Value
Error
Value
+
1x
Error
Value
+
2x
Error
Limit
Weight
(
lbs)
b
Fissile
mass
(
FGE)
b
Curie
limits
(
Ci)
S200
Pipe
overpacks
only
Payload
container
meets
limits
specified
in
Section
3.3
of
the
CH­
TRAMPAC
Yes/
No
UNVENTED
WASTE
PARAMETERS
Aspiration
Method

Option
1

Option
2A

Option
2B

Option
3
Required
Aspiration
Period
days
Option
1
Container
Closed
Time
months
Option
2A,
2B,
or
3
Headspace
H2
Concentration
mol%
Time
Container
Vented
days
HNF­
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HANFORD
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CERTIFICATION
PLAN
TEST
CRITERIA
UFGTP
requirements
are
met
as
documented
in
Section
5.2.5
of
the
CH­
TRAMPAC
Yes/
No
I
certify
that
the
above
container
meets
all
the
requirements
for
shipment
as
stated
in
the
CH­
TRAMPAC,
current
revision.
The
container
is
approved
for

payload
assembly
or

overpacking.

/
(
Print
Name)
(
Sign
Name)
(
Date)
Transportation
Certification
Official
aFollow
instructions
in
Section
6.2.1.2.
bLimits
are
not
applicable
if
container
is
to
be
overpacked.
HNF­
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HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
APPENDIX
D
PAYLOAD
ASSEMBLY
TRANSPORTATION
CERTIFICATION
DOCUMENT
HNF­
2600,
REV
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234
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281
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2005
HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
PAYLOAD
ASSEMBLY
TRANSPORTATION
CERTIFICATION
DOCUMENT
(
PATCD)
a
IDENTIFICATION
PARAMETERS
Shipment
No.
Packaging
OCA
Body/
Lid
No.
Payload
Assembly
Designated
for
Controlled
Shipment?
b

Yes

No
Shipping
Categoryc
Decay
Heat
Limitc
Hydrogen/
Flammable
Gas
Generation
Rate
Limitc
Type
of
Payload

55­
Gallon
Drums

Standard
Pipe
Overpacks

S100
Pipe
Overpacks

S200
Pipe
Overpacks

S300
Pipe
Overpacks

85­
Gallon
Drums

100­
Gallon
Drums

SWBs

TDOP
Transportation
Packaging:

TRUPACT­
II

HalfPACT
Date
ICV
Closed
Time
ICV
Closedd
Certification
Site
BOTTOM
PAYLOAD
ASSEMBLY
COMPOSITION
Container
ID
Weight
(
lbs)
Error
(
lbs)
Decay
Heat
(
watts)
Error
(
watts)
Fissile
Mass
(
FGE)
2
x
Error
(
FGE)
Hydrogen/
Flammable
Gas
Generation
Rate
e,
f,
g
Flammability
Indexf,
g
Subtotal
(
A)
Subtotal
RSS
Error
(
C)
TOP
PAYLOAD
ASSEMBLY
COMPOSITION
(
TRUPACT­
II
Only)
Container
ID
Weight
(
lbs)
Error
(
lbs)
Decay
Heat
(
watts)
Error
(
watts)
Fissile
Mass
(
FGE)
2
x
Error
(
FGE)
Hydrogen/
Flammable
Gas
Generation
Ratee,
f,
g
Flammability
Indexf,
g
Subtotal
(
B)
Subtotal
RSS
Error
(
D)
PAYLOAD
TOTALS
Weight
of
Pallets,
Reinforcing
Plats,
Slip
Sheets,
Guide
Tubes,
Adjustable
Slings,
etc.
(
E)
Total
(
A+
E[+
B
(
TRUPACT­
II
only)])
Weight
lbs
Total
RSS
Weight
Error
lbs
Total
(
A+
B)
Decay
Heat
Watts
Total
RSS
Decay
heat
Error
watts
Total
(
A+
B)
Fissile
Mass
FGE
Total
RSS
Fissile
Mass
Error
FGE
Bottom
Assembly
Weight
plus
Subtotal
RSS
Error
(
A+
C)
(
TRUPACT­
II
Only)
lbs
Top
Assembly
Weight
plus
Subtotal
RSS
Error
(
B+
D)
(
TRUPACT­
II
Only)
lbs
Total
Weight
plus
Total
RSS
Error
lbs
Total
Fissile
Mass
plus
Total
RSS
Error
FGE
Total
Decay
Heat
plus
Total
RSS
Error
watts
HNF­
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2005
HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
PAYLOAD
CERTIFICATION
PARAMETERS
Initials
Decay
Heat
+
Error
of
Each
Analytical
Category
Payload
Container
 
Governing
Limitc
Hydrogen/
Flammable
Gas
Generation
Rate
of
Each
Test
Category
Payload
Container
 
Governing
Limitc,
e
Flammability
Index
of
Each
Payload
Container
meet
the
following
criteria:
0
 
FI
 
50,000f
Payload
Total
Gas
Release
Rate
 
Limit
Calculated
in
accordance
with
CH­
TRAMPAC,
Section
6.2.5h
Bottom
Weight
 
Top
Weight
(
for
TRUPACT­
II)
Total
Weight
plus
RSS
Error
 
7265
lbs
for
TRUPACT­
II;
 
7600
lbs
for
HalfPACT
Decay
Heat
plus
RSS
Error
 
40
Watts
for
TRUPACT­
II;
 
30
watts
for
HalfPACT
Fissile
Mass
(
239Pu
FGE)
plus
RSS
Error
 
FGE
Total
activity
plus
error
for
S100
or
S300
pipe
overpack
payloads
 
406
curies
I
certify
that
the
above
payload
assembly
meets
all
the
requirements
for
shipment
as
stated
in
the
CH­
TRAMPAC,
current
revision.
The
payload
assembly
is
approved
for
shipment.

/
(
Print
Name)
(
Sign
Name)
(
Date)
Transportation
Certification
Official
aFollow
instructions
in
Section
6.2.2
of
the
CH­
TRAMPAC.
bIf
the
payload
is
designated
for
controlled
shipment,
Table
6.2­
5
must
also
be
completed
for
the
shipment
of
this
payload
as
specified
in
Section
6.2.3
of
the
CH­
TRAMPAC.
cNot
applicable
if
mixing
shipping
categories
pursuant
to
Section
4.7.4.
dRequired
only
for
payloads
designated
for
Controlled
Shipment
(
10
days)
eRequired
for
payloads
containing
test
category
payload
containers.
fApplicable
if
mixing
shipping
categories
pursuant
to
Section
4.7.4.
gIf
the
payload
assembly
consists
of
overpacked
configurations,
indicate
not
applicable
(
e.
g.,
"
NA
 
Mixing")
and
record
the
hydrogen/
flammable
gas
generation
rate
and
FI
values
for
each
overpacked
container
on
the
appropriate
OPCTCD.
hApplicable
if
shipping
pursuant
to
Section
6.2.5
of
the
CH­
TRAMPAC.
HNF­
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HANFORD
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WASTE
CERTIFICATION
PLAN
APPENDIX
E
NONDESTRUCTIVE
ASSAY
HNF­
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2005
HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
E.
0
INTRODUCTION
At
the
Hanford
site,
only
nondestructive
assay
(
NDA)
techniques
are
used
in
the
radiological
characterization
and
certification
of
TRU
waste
for
shipment
to
WIPP.
This
appendix
describes
the
Hanford
TRU
Project
requirements
to
meet
the
requirements
specified
in
the
WIPP
contacthandled
waste
acceptance
criteria
(
CH­
WAC)
for
NDA.
Radiochemistry
requirements
are
not
addressed
in
this
appendix.

Radiological
characterization
is
used
to:

 
Identify
and
quantify
the
activity
of
the
ten
WIPP­
tracked
isotopes
(
i.
e.,
241Am,
238Pu,
239Pu,
240Pu,
242Pu,
233U,
234U,
238U,
90Sr
and
137Cs),
 
Identify
and
quantify
the
activity
for
other
isotopes
to
ensure
U.
S.
Department
of
Transportation
(
DOT)
and
certificate
of
compliance
(
C
of
C)
requirements
to
identify
and
quantify
the
isotopes
contributing
to
at
least
95
percent
of
the
total
radiological
hazard.
Identification
and
quantification
of
235U
without
regard
to
total
package
activity
is
necessary
to
meet
DOT
requirements
for
fissile
gram
equivalent
(
FGE)
determination,
 
Ensure
applicable
requirements
for
decay
heat,
239Pu
FGE,
and
239Pu
equivalent
activity
(
PE­
Ci)
are
met,
and
 
Demonstrate
that
the
waste
being
disposed
of
at
WIPP
meets
the
radiological
definition
of
TRU
waste.

Acceptable
knowledge
(
AK)
may
be
used
to
supplement
NDA
for
hard­
to­
detect
radionuclides
(
e.
g.,
90Sr
and
234U),
when
poor
counting
statistics
exist,
etc.
The
requisite
data
on
isotopic
ratios
and
quantities
will
be
derived
from
AK
(
see
subsection
E.
1),
NDA,
or
both,
using
CBFOapproved
NDA.

The
SPO
must
technically
justify
the
AK,
and
each
facility
must
technically
justify
that
the
NDA
techniques,
instruments,
and
procedures
used:

 
Are
appropriate
for
the
specific
waste
stream
and
waste
content
code
descriptions
being
assayed,
 
Will
result
in
unbiased
values
for
the
activity
and
mass
of
the
WIPP
radionuclide
inventory,
and
 
Are
initiated,
revised,
reviewed,
maintained,
controlled
in
accordance
with
Hanford
TRU
Project
procedures.

Controlled
changes
to
radioassay
(
NDA
or
radiochemistry)
related
plans
or
procedures
shall
be
managed
through
the
document
control
process
described
in
the
QAPD.
The
Site
Project
Manager
and
the
Site
QA
Officer
shall
review
all
such
changes
and
report
to
the
CBFO
those
changes
that
could
impact
compliance
with
the
criteria
in
this
Certification
Plan.
The
Site
Project
Manager
shall
ensure
that
site­
approved
changes
to
radioassay­
related
plans
or
procedures
affecting
either
the
performance
criteria
or
data
quality
of
certified
systems/
processes
are
not
used
in
the
collection
of
waste
certification
data
prior
to
CBFO's
review
and
approval.
Related
testing,
calibration,
and
training
performed
in
accordance
with
these
site­
approved
changes,
however,
are
not
precluded
from
being
conducted
prior
to
CBFO's
review
and
HNF­
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HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
approval.
(
Memorandum
from
CBFO
to
Distribution,
CBFO:
NTP:
RMK:
VW:
02­
2734:
UFC5822,
July
29,
2002.)

E.
1
RADIONUCLIDE
ISOTOPIC
RATIOS
Direct
measurement
using
WIPP­
certified
NDA
equipment
of
all
containers
in
a
waste
stream
has
been
selected
as
the
methodology
to
perform
radiological
characterization
of
TRU
waste
at
the
Hanford
site.
It
is
recognized
that
certain
nuclides
(
e.
g.,
90Sr
and
234U)
cannot
be
quantified
using
NDA
and
that
technical
reasons
may
cause
the
NDA
for
certain
waste
to
be
invalid
(
e.
g.,
poor
counting
statistics).
Under
these
circumstances,
AK
will
be
used
to
complete
radiological
characterization.

E.
1.1
Methods
for
Confirmation
of
Isotopic
Ratio
Acceptable
Knowledge
The
Hanford
site
requires
that
all
containers
of
TRU
waste
be
assayed
to
perform
radiological
characterization
of
that
waste.
The
batch
data
reports
shall
contain
results
of
isotopic
measurements.
The
SPO
shall
correlate
the
results
of
actual
measurements
to
AK.
Reference
E22
shall
describe
the
documentation
and
discrepancy
resolution
requirements
for
this
correlation.

Because
234U
and
90Sr
cannot
be
detected
using
the
NDA
systems
currently
in
use
at
the
Hanford
site,
the
means
and
methodology
to
quantify
these
isotopes
from
other
measured
isotopes
shall
be
technically
justified
in
the
AK
documentation
described
below.
If
measured
isotopic
results
are
not
used,
the
use
of
AK
must
be
either
included
with
or
referenced
in
NDA
batch
data
reports.
Examples
of
this
quantification
include
using
isotopic
ratios
to
calculate
234U
from
the
measured
235U
(
and
possibly
238U)
and
90Sr
from
the
measured
137Cs.
When
the
activity
of
an
isotope
is
scaled
or
correlated
from
the
measured
value
of
another
isotope
(
e.
g.,
90Sr
calculated
from
measured
137Cs
or
234U
from
235U
or
238U),
the
NDA
batch
data
report
shall
contain
sufficient
information
to
independently
perform
or
repeat
that
calculation.

The
acceptance
or
rejection
of
identified
isotopes
or
unidentified
peaks
is
usually
part
of
routine
analytical
procedures
and
is
not
normally
subject
to
AK
requirements.
Examples
of
this
include
using
confirmatory
peaks
or
correlation
to
demonstrate
the
absence
or
presence
of
certain
isotopes
or
elimination
of
a
nuclide
or
peak
based
upon
high
counting
error.
Facility
procedures
shall
specify
the
means
to
document
such
rejection,
acceptance,
or
correlation.

If
any
of
the
ten
WIPP­
tracked
isotopes
are
determined
not
to
be
present
in
a
waste
stream
on
the
basis
of
AK,
this
shall
be
technically
justified
in
the
AK.

E.
1.2
Acceptable
Knowledge
(
AK)
Documentation
E.
1.2.1
Required
Elements
The
use
of
AK
information
concerning
the
radiological
composition
of
a
waste
stream
will
be
documented
either
in
the
AK
summary
report
for
the
waste
characterization
of
the
waste
stream
or
in
another
controlled
document
approved
by
the
SPM.
Should
this
information
be
contained
in
AK
package(
s)
prepared
to
meet
other
general
waste
characterization
requirements,
it
need
not
HNF­
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5/
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HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
be
duplicated
in
other
controlled
documents
that
address
the
radiological
properties
of
the
waste
stream.
The
following
information
shall
be
included
as
part
of
the
written
AK
record,
as
described
in
WMP­
400,
Section
7.1.9:

 
Map
of
the
Hanford
site
with
the
areas
and
facilities
involved
in
TRU
mixed
waste
generation,
treatment,
and
storage
identified,
 
Facility
mission
description
as
related
to
radionuclide­
bearing
materials
and
their
management
(
e.
g.,
routine
weapons
production,
fuel
research
and
development,
and
experimental
processes),
 
Description
of
the
specific
facility
locations
(
such
as
the
area
or
building)
and
operations
relative
to
the
isotopic
composition
of
the
TRU
wastes
they
generated
(
e.
g.,
plutonium
recovery,
weapons
fabrication,
pyrochemical
operations,
and
waste
incineration),
 
Waste
identification
or
categorization
schemes
used
at
the
facility
relevant
to
the
waste
material's
isotopic
distribution
(
e.
g.,
the
use
of
codes
that
correlate
to
a
specific
isotopic
distribution),
and
a
description
of
the
isotopic
composition
of
each
waste
stream,
 
Information
regarding
the
waste's
physical
and
chemical
composition
that
could
affect
the
isotopic
distribution
(
e.
g.,
processes
used
to
remove
ingrown
241Am
or
alter
its
expected
contribution
based
solely
on
radioactive
decay
kinetics),
 
Statement
of
all
numerical
adjustments
applied
to
derive
the
material's
isotopic
distribution
(
e.
g.,
scaling
factors,
decay/
ingrowth
corrections
and
secular
equilibrium
considerations),
 
Specification
of
the
isotopic
ratios
for
the
ten
WIPP­
tracked
radionuclides
(
241Am,
238Pu,
239Pu,
240Pu,
242Pu,
233U,
234U,
238U,
90Sr,
and
137Cs)
and,
if
applicable,
other
radionuclides
such
that
at
least
95
percent
of
the
total
radiological
hazard
in
a
waste
stream,
waste
stream
subpopulation,
and
container
basis
is
reported.
Additionally,
the
isotopic
ratios
for
radionuclides
that
are
neither
one
of
the
ten
WIPP­
tracked
isotopes
nor
otherwise
contribute
to
95
percent
of
the
total
radiological
hazard
must
be
established
and
technically
justified
in
the
AK
documentation
if
either
of
the
below
conditions
are
met:

1.
The
radionuclide
contributes
to
FGE
(
e.
g.,
237Np
or
235U)

2.
The
radionuclide
is
used
to
scale
one
of
the
ten
WIPP­
tracked
isotopes.

The
type
and
quantity
of
supporting
documentation
may
vary
by
waste
stream
and
shall
be
compiled
in
a
written
record
that
shall
include
a
summary
identifying
all
sources
of
information
used
to
delineate
the
waste
stream's
isotopic
distribution.
The
basis
and
rationale
for
the
delineation
shall
be
clearly
summarized
in
an
AK
report
and
traceable
to
referenced
documents.
Assumptions
made
in
this
delineation
shall
be
identified.

E.
1.2.2
Supplemental
Acceptable
Knowledge
Information
The
SPO
shall
obtain
supplemental
AK
information,
dependent
on
availability.
The
amount
and
type
of
this
information
cannot
be
mandated,
but
the
SPO
shall
collect
information
as
appropriate
to
support
documentation
of
the
waste's
isotopic
distribution.
This
information
will
be
used
to
compile
the
waste's
AK
written
record,
in
accordance
with
WMP­
400,
Section
7.1.9.
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Supplemental
AK
documentation
that
may
be
used
includes,
but
is
not
limited
to,
information
from
the
following
sources:

 
Safeguards
&
Security,
Materials
Control
&
Accountability,
and
other
nuclear
materials
control
systems
or
programs
and
the
data
they
generated,
 
Reports
of
nuclear
safety
or
criticality,
or
accidents/
excursions
involving
the
use
of
special
nuclear
material
(
SNM)
or
nuclear
material,
 
Waste
packaging,
waste
disposal,
building
or
nuclear
material
management
area
logs
or
inventory
records,
and
available
databases
that
provide
information
on
SNM
or
nuclear
materials,
 
Test
plans,
research
project
reports,
or
laboratory
notebooks
that
describe
the
radionuclide
content
of
materials
used
in
experiments,
 
Information
from
facility
personnel
(
e.
g.,
documented
interviews),
and
 
Historical
analytical
data
relevant
to
the
isotopic
distribution
of
the
waste
stream.

E.
1.2.3
Discrepancy
Resolution
If
there
is
a
discrepancy
between
AK
information
related
to
isotopic
ratios
or
composition,
the
SPO
will
evaluate
the
sources
of
the
discrepancy
to
determine
if
the
discrepant
information
is
credible.
Information
that
is
not
credible
or
information
that
is
limited
in
its
applicability
to
WIPP
characterization
will
be
identified
as
such,
and
the
reasons
for
dismissing
it
will
be
justified
in
writing.
Limitations
concerning
the
information
will
be
documented
in
the
AK
record
and
summarized
in
the
AK
report.
If
discrepancies
result
in
a
change
to
the
original
determinations,
the
AK
summary
will
be
updated.
Discrepancy
reporting
and
resolution
shall
be
documented
in
accordance
with
reference
E22.

Positive
identification
and
quantification
of
any
isotope
previously
identified
in
AK
as
not
being
present
shall
be
treated
as
a
discrepancy
and
documented
in
accordance
with
reference
E22.

If
a
discrepancy
cannot
be
resolved,
the
site
will
perform
direct
measurements
for
the
impacted
population
of
containers.

E.
2
DATA
QUALITY
OBJECTIVES
The
data
quality
objectives
(
DQOs)
for
WIPP­
certifiable
radiological
characterization
data
are
established
in
section
3.3
and
summarized
in
section
A.
3
of
the
CH­
WAC.
They
are
summarized
below
in
Table
E­
1
as
they
apply
to
individual
payload
containers.
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Table
E­
1
Data
Quality
Objectives
for
NDA
Requirement
DQO
Confidencea
TRU
 ­
activity
concentration
>
100
nCi/
gb
activity
>
LLD
N/
A
Fissile
mass
 
FGE
limit
FGE
+
2 TMU
(
FGE)
 
FGE
limit
97.5%

Decay
Heat
(
DH)
 
CH­
TRAMPAC
limit
DH
+
1
 TMU
(
DH)
 
LCH­
TRAMPAC
84%
aConfidence
means
the
statistical
level
of
confidence
that
the
limit
is
exceeded
or
not
exceeded
depending
on
the
requirements
of
the
individual
DQOs.
The
confidence
is
derived
from
the
specified
DQOs
which
assumes
contributions
to
total
measurement
uncertainty
(
TMU)
are
normally
distributed.
bTRU
waste
determinations
shall
be
in
accordance
with
the
policy
for
management
of
TRU
alpha
activity
concentration
when
overpacking
waste
containers.

There
are
no
stipulated
DQOs
for
PE­
Ci
or
individual
isotope
activities
(
except
as
they
impact
the
requirements
listed
above).
However,
at
a
minimum,
NDA
programs
must
be
capable
of
identifying,
measuring,
and
reporting
the
presence
or
absence
of:

 
The
ten
radionuclides
identified
in
subsection
3.3.1
for
tracking
of
the
WIPP
radionuclide
inventory
(
see
subsection
E.
1.1
above
for
discussion
of
hard­
to­
detect
nuclides),
 
235U,
in
order
to
calculate
FGE,
as
required
in
subsection
3.3.3
for
compliance
with
transportation
requirements,
 
Other
radionuclides
that
contribute
to
at
least
95
percent
of
total
radiological
hazard,
as
specified
in
subsection
3.3.1,
for
compliance
with
transportation
requirements,
and
 
Other
radionuclides
that
contribute
to
FGE
or
decay
heat
(
e.
g.,
241Pu
or
237Np
if
AK
indicates
the
presence
of
such
contributors)
or
any
radionuclide
used
to
scale
one
of
the
otherwise
reportable
radionuclides
(
e.
g.,
235U
for
234U).

In
support
of
the
above
requirements,
each
facility
must
evaluate,
document,
and
technically
justify
the
following
determinations.

1.
Lower
Limit
of
Detection:
The
lower
limit
of
detection
(
LLD)
for
each
NDA
system
must
be
determined.
Instruments
performing
TRU
waste/
low­
level
waste
discrimination
measurements
must
have
an
LLD
of
100
nCi/
g
or
less.
Facility­
specific
environmental
background
and
container­
specific
interferences
must
be
factored
into
LLD
determinations.
LLD
is
that
level
of
radioactivity
which,
if
present,
yields
a
measured
value
greater
than
the
critical
level
with
a
95
percent
probability,
where
the
critical
level
is
defined
as
that
value
which
measurements
of
the
background
will
exceed
with
5
percent
probability.
Because
LLD
is
a
measurement­
based
parameter,
it
is
not
feasible
to
calculate
LLD
for
radionuclides
that
are
not
determined
primarily
by
measurement
(
e.
g.,
90Sr
and
234U).
In
such
cases,
the
facility
shall
derive
the
equivalent
of
an
LLD
(
i.
e.,
a
reporting
threshold
for
a
radionuclide(
s),
when
it
is
technically
justified).
This
value
may
be
based
on
decay
kinetics,
scaling
factors,
or
other
scientifically
based
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relationships
and
must
be
adequately
documented.
For
purposes
of
reporting
radionuclide
data
in
the
WWIS,
this
value
will
be
the
equivalent
of
an
LLD.
References
E3
and
E4
provide
information
in
developing
the
LLD.
The
method(
s)
for
determining
LLD
shall
be
documented
in
a
report
to
the
SPO
and
approved
by
the
SQAO.

2.
Total
Measurement
Uncertainty
(
TMU):
The
method
used
to
calculate
the
TMU
for
the
quantities
in
table
E­
1
must
be
documented
and
technically
justified
for
each
CBFO­
certified
NDA
system.
It
is
permissible
to
combine
reports
for
like
or
similar
systems
if
the
TMU
is
justified
to
be
identical
or
if
any
differences
are
clearly
identified
and
do
not
otherwise
affect
other
portions
of
TMU.
The
likeness
or
similarity
of
the
systems
must
be
technically
justified
in
the
TMU
report.
Compliance
with
this
requirement
will
be
evaluated
in
reviews
of
the
TMU
documentation
package
for
each
assay
system
by
CBFO.
General
guidance
for
determining
the
TMU
is
provided
in
references
E5
and
E6.
TMU
shall
be
properly
justified
and
calculated
and
documented
in
a
report
to
the
SPO
and
approved
by
the
SQAO.

3.
Calibration.
Each
NDA
system
shall
be
calibrated
before
initial
use.
During
calibration
(
or
recalibration),
system
correction
factors
shall
be
established
and
algorithms
adjusted
such
that
the
value
of
%
R
(
percent
recovery)
is
set
equal
to
100
percent
(
i.
e.,
the
system
is
calibrated
to
100%
R).
When
calibrating
NDA
instruments,
a
calibration
curve
is
usually
fitted
to
a
number
of
data
points
obtained
with
calibration
sources.

The
range
of
applicability
of
system
calibrations
must
be
specified
in
facility
procedures.
The
matrix/
source
surrogate
waste
combination(
s)
used
for
calibration
shall
be
representative
of
the
activity
range(
s)
or
gram
loading(
s),
and
relevant
waste
matrix
characteristics
(
e.
g.,
densities,
moderator
content,
container
size)
planned
for
measurement
by
the
system.

Calibration
and
recalibration
shall
be
documented
in
a
report
to
the
SPO
and
approved
by
the
SQAO.
Individual
components
or
functions
(
e.
g.,
separate
detectors
or
reference
peak)
may
require
individual
calibration.
Calibration
of
supporting
systems
(
e.
g.,
gamma
system
used
solely
for
isotopic
measurements
to
support
calorimetry
or
neutron
measurements)
may
be
limited
to
applicable
portions
of
the
calibration
for
that
instrument
(
e.
g.,
just
energy).

Calibration(
s)
shall
be
performed
in
accordance
with
consensus
standards
(
see
NDA
quality
control
[
QC]
requirements
below)
when
such
standards
exist.
For
calorimetry,
calibration
shall
be
performed
in
accordance
with
reference
E17.
If
consensus
standards
are
not
used,
full
documentation
of
the
calibration
technique
must
be
provided
to
and
approved
by
CBFO
before
performing
WIPP­
related
assays.
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4.
Calibration
Standards
(
and
Sources):
Sources
used
for
calibration
and
calibration
confirmation
shall
meet
the
requirements
listed
below.
Sources
used
for
instrument
performance
measurements
are
not
subject
to
these
requirements
but
shall
be
well­
characterized.

a.
Primary
calibration
standards
(
or
sources)
shall
be
obtained
from
suppliers
maintaining
a
nationally
accredited
measurement
program.
When
primary
standards
are
not
available,
the
standards
used
shall
be
correlated
with
primary
standards
obtained
from
a
nationally
accredited
measurement
program.
The
Hanford
TRU
Project
defines
"
suppliers
maintaining
a
nationally
accredited
measurement
program"
as
associated
with
NDA
and
radioactive
sources
to
include,
but
not
be
limited
to,
programs
associated
with
or
qualified
by
and
in
descending
priority:

 
National
Institute
of
Standards
and
Technology
(
NIST)
 
New
Brunswick
Laboratory
(
NBL)
 
Sandia
National
Laboratory
(
SNL)
 
Los
Alamos
National
Laboratory
(
LANL)

b.
Primary
calibration
standards
cannot
exceed
the
authorization
or
approval
for
that
organization
as
identified
in
the
applicable
measurement
program
(
e.
g.,
relative
to
isotopes,
matrix,
form,
DC
voltage,
etc.).
Correlation
to
a
primary
standard
must
also
be
within
the
authorization
or
approval
limitations
for
the
primary
standard(
s)
being
used.
The
Hanford
site
defines
"
Primary
calibration
standards
or
sources"
as
being
standards
or
sources
for
which
the
value
of
those
standards
or
sources
is
certified
directly
by
and
in
one
of
the
programs
identified
in
4.
a
immediately
above.

c.
Correlation
of
standards
must
be
documented,
approved
by
the
SQAO,
and
transmitted
to
the
SPO.
Equipment
critical
to
the
correlation
of
a
standard
to
primary
standards
obtained
from
a
nationally
accredited
measurement
program
must
have
been
calibrated
and
maintained
using
standards
that
meet
the
same
criteria.
Standards
used
for
correlation
cannot
be
the
same
ones
used
for
calibration
of
the
equipment
used
to
establish
the
correlation.
The
sources
or
standards
must
be
at
the
same
or
higher
level
to
which
the
correlation
is
being
established.

5.
Calibration
Verification:

a.
Notwithstanding
the
need
to
calibrate
individual
components
after
replacement,
changes,
or
adjustments
(
e.
g.,
energy
calibration
of
a
detector),
verification
of
the
NDA
system's
calibration
shall
be
performed
after
any
one
of
the
following
occurs:
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(
1)
Replacement
of
the
measurement
system's
major
components
(
e.
g.,
detector,
neutron
generator,
or
supporting
electronic
components
that
have
the
capacity
to
affect
data),

(
2)
Major
system
repairs
and/
or
modifications
(
e.
g.,
detector
reconditioning
or
replacement
of
key
mechanical
components
that
have
the
capacity
to
affect
data),

(
3)
Significant
changes
to
the
system's
software,
or
(
4)
Relocation
of
the
system.

b.
Calibration
verification
shall
consist
of
demonstrating
that
the
system
is
within
the
range
of
acceptable
operation.
Calibration
verification
is
an
overall
performance
check
of
the
ability
of
the
system
as
a
whole
to
produce
consistent
results
(
e.
g.,
combined
overall
check
of
a
gamma
system's
calibrations
for
energy,
efficiency,
etc.).
Secondary
standards
can
be
used
for
the
calibration
verification
if
their
performance
has
been
correlated
with
the
calibration
standard
(
see
item
4,
above).
If
a
verification
of
the
measurement
system's
calibration
or
other
test
demonstrates
that
the
system's
response
has
significantly
changed,
a
recalibration
of
the
system
shall
be
performed.
A
system
calibration
may
be
performed
in
lieu
of
calibration
verification.

c.
Calibration
verification
is
typically
duplicate
measurements
of
a
single
data
point
for
each
calibration.
It
is
not
always
necessary
to
verify
each
concurrent
calibration,
or
the
calibration
verification
may
be
limited
to
that
for
the
individual
component(
s).

(
1)
When
each
calibration
is
not
verified,
the
report
of
the
calibration
verification
must
include
technical
justification
for
any
intentional
omissions.

(
2)
Examples
of
when
such
partial
calibration
verification
would
be
appropriate
include
when
only
an
energy
calibration
of
a
detector
is
required
(
i.
e.,
efficiency
is
not
affected)
or
a
hardware
change
that
does
not
affect
data
calculation.

(
3)
Examples
of
when
a
full
calibration
verification
or
when
all
concurrent
calibrations
are
required
to
undergo
calibration
verification
include
software
upgrade
or
replacement
of
components
affecting
data
calculations.

d.
Calibration
verification
shall
be
documented
in
a
report
to
the
SPO
and
approved
by
the
SQAO.
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6.
Calibration
Confirmation:
To
confirm
that
the
calibration
of
the
NDA
system
was
correctly
established,
the
accuracy
and
precision
of
the
system
are
determined
after
each
calibration
(
or
recalibration)
by
performing
replicate
measurements
of
a
non­
interfering
matrix.
Calibration
confirmation
replicate
measurements
shall
be
performed
on
containers
of
the
same
nominal
size
as
those
in
which
actual
waste
is
assayed
and
according
to
approved
waste
assay
procedures.
The
number
of
replicate
measurements
to
be
performed
shall
be
documented
and
technically
justified.
The
replicate
measurements
shall
be
performed
using
calibration
standards
or
sources
(
see
above)
that
span
the
range
of
use.
The
calibration
standards
used
for
calibration
confirmation
shall
not
be
the
same
as
those
used
for
the
system
calibration.

Accuracy
is
reported
as
percent
recovery
(%
R).
The
acceptance
criteria
for
accuracy
shall
be
within
±
30
percent
of
nominal
source
strength
in
a
noninterfering
matrix.
Normally,
a
minimum
of
two
source
strengths
is
required­­
one
from
the
lower
one­
third
of
the
range,
and
one
from
the
upper
one­
third
of
the
range.
A
single­
source
strength
may
be
used
only
if
the
operating
range
is
restricted
to
either
small
mass
loadings
(
i.
e.,
a
range
of
0­
20
g
WG
Pu)
or
the
calibration
range
is
small
(
i.
e.,
the
range
spans
less
than
20
g
WG
Pu).
Precision
is
reported
as
percent
relative
standard
deviation
(%
RSD).
The
%
RSD
shall
not
exceed
the
values
listed
in
table
E­
2
for
the
corresponding
number
of
replicate
measurements
in
a
non­
interfering
matrix.
Calibration
confirmation
shall
be
documented
in
a
report
to
the
SPO
and
approved
by
the
SQAO.

Table
E­
2
Upper
Limits
for
%
RSD
vs.
Number
of
Replicates
a
Number
of
Replicates
2
3
4
5
6
7
8
9
10
11
12
13
14
15
Max
%
RSD
1.8
6.6
10.0
12.3
14.0
15.2
16.2
17.1
17.7
18.3
18.8
19.3
19.7
20.0
a
The
values
listed
for
maximum
%
RSD
are
derived
from
the
measured
standard
deviation
of
the
replicate
measurements
using
the
formula:

%
100
1
)
292
.
0
(
%
100
2
1
,
05
.
0
 
 
 
<
 
 

n
s
n
 
µ
where
s
is
the
measured
standard
deviation,
n
is
the
number
of
replicates,
µ
is
the
true
value,
 2
0.05,
n­
1
is
the
critical
value
for
the
upper
5%
tail
of
a
one
sided
chi­
squared
distribution
with
n­
1
degrees
of
freedom,
and
0.292
corresponds
to
a
95%
upper
confidence
bound
on
the
true
system
precision
limit
of
29.2%.
This
formula
may
be
used
to
calculate
the
maximum
%
RSD
if
more
than
15
replicate
analyses
are
performed.
A
minimum
of
2
replicates
must
be
analyzed
and
documented.

Use
of
alternate
limits
for
accuracy
and
precision
must
be
technically
justified
and
approved
by
CBFO
before
certification
of
the
waste.
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E.
3
QUALITY
CONTROL
This
appendix
documents,
defines,
and
describes
the
additional
QA
requirements
for
NDA
that
must
be
implemented
by
and
in
facility
calibration
and
operating
procedures.
Each
NDA
technique
used
for
NDA
of
TRU
waste
must
be
performed
in
accordance
with
calibration
and
operating
procedures
that
have
been
written,
approved,
and
controlled
by
the
facility
and
the
SPO.
Procedures
shall
contain
applicable
quality
controls
as
described
below
and
must
specify
the
qualitative
and
quantitative
acceptance
criteria
and
corrective
action
to
take
if
these
criteria
are
not
met.
In
accordance
with
references
E27
through
E29,
NDA
personnel
initiate
a
nonconformance
report
(
NCR)
and/
or
corrective
action
report
(
CAR),
as
appropriate,
if
final
reported
background
measurements,
instrument
performance
measurements,
interfering
matrix
checks,
or
trending
analyses
do
not
meet
acceptance
criteria.
All
background
and
instrument
performance
measurements
shall
be
documented.

E.
3.1
General
Requirements
1.
NDA
Training:
Only
appropriately
trained
and
qualified
personnel
shall
be
allowed
to
perform
NDA
and
data
validation/
review.
Standardized
training
requirements
for
NDA
personnel
shall
be
based
upon
existing
industry
standardized
training
requirements
(
e.
g.,
references
E8
and
E9)
and
shall
meet
the
specifications
in
the
reference
E2.
Qualification
of
NDA
personnel
shall
be
completed
in
accordance
with
references
E23
and
E24.
Requalification
shall
be
based
upon
evidence
of
continued
satisfactory
performance
and
must
be
performed
at
least
every
two
years
in
accordance
with
references
E23
and
E24.

2.
Software
QC
Requirements:
Reference
E25
describes
the
Hanford
TRU
Project's
software
QA
program
and
incorporates
requirements
from
references
E2
(
QAPD,
section
6.0)
and
E30.

3.
Comparison
Programs:
Sites
using
NDA
systems
shall
participate
in
any
relevant
measurement
comparison
program(
s)
sponsored
or
approved
by
the
CBFO.
Such
programs
may
be
conducted
as
part
of
the
NDA
performance
demonstration
program
(
PDP)
(
references
E7
and
E10)
or
through
other
third
parties.
Participation
in
a
measurement
comparison
program
is
not
required
if
CBFO
has
not
sponsored
or
approved
such
a
program
for
that
waste
matrix
or
configuration.
Participation
in
the
Calorimetry
Exchange
Program
administered
by
NBL
is
not
required
from
a
WIPP
perspective.
However,
if
WIPP­
certified
calorimeters
participate
in
this
program
(
e.
g.,
to
meet
safeguards
or
other
business
practice
requirements),
the
results
shall
also
be
transmitted
to
TRU
Project
records
to
document
participation
in
a
measurement
comparison
program.

4.
Control
Limits:
As
recognized
by
reference
E15,
initial
establishment
of
statistical
control
limits
may
have
to
be
based
upon
a
limited
population
of
measurement
results.
Control
limits
should
be
updated
as
conditions
warrant
or
change
(
e.
g.,
increase
in
sample
population,
changes
over
time,
etc.).
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5.
Definitions:
The
Hanford
TRU
Project
uses
the
following
definitions
relative
to
performance
of
periodic
QC
related
measurements:

Operational
Day
(
also
"
when
in
operation"):
A
24­
hour
period
in
which
the
system
is
to
be
used
to
perform
measurements
for
TRU
wastes.

Operational
Week:
Seven
consecutive
days
starting
at
7
a.
m.
on
Monday
in
which
the
system
performed
WIPP­
related
measurements
on
one
or
more
days
in
that
week.

Six­
month
period
(
as
used
in
interfering
matrix
checks):
The
six
calendar
months,
through
the
last
day
of
the
sixth
month,
during
which
the
system
is
used.
This
period
starts
the
day
of
the
first
instrument
performance
measurement
performed
on
or
after
May
17,
2002,
the
completion
of
the
previous
six­
month
period,
or
placing
the
system
in
service,
as
appropriate.
Once
started,
the
sixmonth
period
cannot
be
extended
due
to
periods
of
the
system
being
out
of
service
or
inactive,
although
the
facility
may
end
the
period
earlier
(
e.
g.,
if
a
new
system
calibration
is
required,
suspension
of
operations,
etc.).

E.
3.2
NDA
Quality
Control
Requirements
for
GEA
Systems
E.
3.2.1
Recommended
Consensus
Standards
The
assay
procedures
related
requirements
and
guidance
cited
in
certain
American
Society
for
Testing
and
Materials
(
ASTM)
and
American
National
Standards
Institute
(
ANSI)
standards
(
references
E8,
E11,
E13
and
E15)
and
NRC
standard
practices
and
guidelines
(
reference
E16)
as
referenced
in
this
appendix
are
recommended
for
use
at
all
Hanford
facilities.
Since
these
consensus
standards
address
a
multitude
of
operating
systems,
environments,
regulatory
requirements,
etc.,
it
is
not
practical
to
accept
any
of
these
standards
in
their
entirety.

E.
3.2.2
Quality
Control
Requirements
The
information
below
summarizes
the
minimum
QC
requirements
related
to
GEA
systems:

1.
Background
Measurements:
Must
be
performed
and
recorded
at
least
once
per
operational
day
unless
specific
approval
for
a
less
frequent
period
is
obtained
from
CBFO.
Contributions
to
background
due
to
radiation
from
nearby
radiation­
producing
equipment,
standards,
or
wastes
must
be
carefully
controlled.
More
frequent
background
measurements
must
be
performed
if
the
background
will
vary
significantly
within
a
single
day
or
shift.
Background
measurements
are
not
required
when
the
system
is
out
of
service
or
for
systems
used
solely
for
isotopic
measurements.

Background
measurements
are
normally
performed
before
the
first
use
of
the
system
for
WIPP­
related
measurements
on
a
given
day.
However,
for
measurements
made
during
off­
hours,
the
period
of
validity
of
the
background
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measurement
may
carry
over
into
the
next
calendar
day,
but
only
if
the
time
elapsed
from
the
last
background
measurement
is
less
than
24
hours.

Individual
(
i.
e.,
daily
or
more
frequent)
background
measurements
shall
be
evaluated
against
acceptance
limits
established
in
facility
procedures.
Facility
procedures
shall
also
define
the
actions
to
take
if
background
measurements
result
in
data
that
are
outside
the
acceptable
range.

2.
Instrument
Performance
Measurements:
Instrument
performance
measurements
on
operable
instruments
or
systems
must
be
performed
and
recorded
at
least
once
per
operational
day.
Instrument
performance
measurements
for
systems
used
for
quantitative
measurements
shall
include,
but
are
not
limited
to,
efficiency
checks,
matrix
correction
checks,
peak
position,
and
resolution
checks,
as
applicable.
Instrument
performance
measurements
are
not
required
when
the
system
is
out
of
service.
Both
radioactive
sources
and
surrogate
waste
matrix
containers
(
both
non­
interfering
and
interfering)
may
be
used.

Instrument
performance
measurements
are
normally
performed
before
the
first
use
of
the
system
for
WIPP­
related
measurements
on
a
given
day.
However,
for
measurements
made
during
off­
hours,
the
period
of
validity
of
the
instrument
performance
measurements
may
carry
over
into
the
next
calendar
day,
but
only
if
the
time
elapsed
from
the
last
set
of
instrument
performance
measurements
is
less
than
24
hours.

Individual
(
i.
e.,
daily
or
more
frequent)
instrument
performance
measurements,
regardless
of
whether
or
not
an
interfering
matrix
is
used
for
these
measurements,
shall
be
verified
to
be
within
acceptance
limits
in
accordance
with
table
E­
3,
below,
before
permitting
any
routine
operations
(
e.
g.,
measurements
for
actual
waste
characterization).
If
instrument
performance
measurements
result
in
data
that
are
outside
the
acceptable
range,
the
required
responses
in
Table
E­
3
shall
be
followed.

Instrument
performance
measurements
for
gamma
systems
used
solely
for
isotopic
measurements
(
e.
g.,
to
support
calorimetry
or
neutron
measurements)
may
consist
of
separate
instrument
performance
measurements
(
e.
g.,
energy
and
resolution)
or
may
be
part
of
an
overall
combined
system
instrument
performance
measurement
for
the
combined
gamma­
calorimeter/
neutron
system.
Independent
instrument
performance
measures
are
subject
to
the
requirements
and
acceptance
criteria
of
Table
E­
3,
and
combined
instrument
performance
measurements
are
subject
to
the
requirements
from
the
applicable
section
(
e.
g.,
section
E.
3
or
E.
4).
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Table
E­
3
Control
Limits
(
Range
of
Applicability)
for
Instrument
Performance
Measurements
of
Gamma
and
Neutron
Systems
Category
Acceptability
Range
a
Required
Actions
d
Acceptable
|
Result
|
c
 
2 
b
No
action
required.
Warning
2 
b
<
|
Result
|
c
 
3 
b
The
instrument
performance
measurement
may
be
rerun
no
more
than
twice
(
i.
e.,
maximum
of
three
total
measurements).
If
a
repeat
instrument
performance
measurement
results
in
data
within
±
2 ,
the
additional
instrument
performance
measurement
shall
be
documented
and
work
may
continue.
If
the
system
does
not
fall
within
±
2 
after
a
maximum
of
two
reruns
instrument
performance
measurements,
then
the
required
response
for
the
Action
Range
shall
be
followed.
Action
|
Result
|
c
>
3 
b
Work
shall
stop,
and
the
occurrence
shall
be
documented
as
an
NCR
or
CAR
and
appropriately
dispositioned.
The
NDA
system
shall
be
removed
from
service
pending
successful
resolution
of
all
necessary
actions,
and
all
assays
performed
since
the
last
acceptable
instrument
performance
measurements
are
suspect,
pending
satisfactory
resolution.
If
the
corrective
action
includes
the
adjustment,
maintenance,
repair
or
replacement
of
any
system
component,
recalibration
or
calibration
verification
is
required
before
returning
the
system
back
to
service.
a
Reference
E15.
Alternative
control
limits
may
be
used
only
with
prior
approval
by
CBFO.
bThe
standard
deviation
(
 )
is
only
based
on
the
reproducibility
of
the
data
check
measurements
themselves.
This
is
not
TMU.
The
standard
deviation
may
be
periodically
updated
to
account
for
changes
in
system
response
over
time.
The
initial
acceptability
range
and
any
subsequent
changes
shall
be
documented
and
transmitted
to
the
SPO.
If
the
standard
deviation
is
not
calculated
as
the
square
root
of
the
variance
as
calculated
from
ANSI
N15.36­
1994
(
Annex
A,
Equation
A.
1),
the
reference
for
the
equation
that
is
used
must
be
provided
to
and
approved
by
CBFO.
When
control
limits
are
calculated
using
alternative
methodologies,
±
2 
corresponds
to
the
calculated
upper
and
lower
warning
limits
and
±
3 
corresponds
to
the
calculated
upper
and
lower
action
limits.
Only
the
positive
range
for
the
warning
and
action
are
applicable
for
resolution
control
limits.
cAbsolute
Value
dIf
failure
of
an
instrument
performance
check
is
due
to
a
procedural
noncompliance
(
e.
g.,
incorrect
or
no
source
used),
a
CAR
will
be
issued.
Additional
instrument
performance
measurement(
s)
shall
be
performed
in
accordance
with
procedural
requirements.
If
these
additional
instrument
performance
measurements
meet
the
acceptance
criteria,
NDA
operations
may
continue
while
the
CAR
is
processed.
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3.
Interfering
Matrix
Checks:
In
addition
to
the
daily
instrument
performance
measurements,
at
least
once
during
the
operational
week
an
interfering
matrix
must
be
used
to
assess
the
long­
term
stability
of
the
NDA
instrument's
matrix
correction.
Surrogate
waste
containers
must
reflect
the
type
of
waste
(
e.
g.,
debris,
ash)
currently
being
assayed.
Radioactivity
standards
and
interfering
matrices
must
be
selected
such
that,
over
a
six­
month
period,
the
operating
range
of
the
assay
system
is
tested
in
each
applicable
surrogate
waste
matrix.
Interfering
matrix
checks
are
not
required
for
gamma
systems
used
solely
for
isotopic
measurements
to
support
calorimetry
or
neutron
measurements.

An
applicable
surrogate
waste
matrix
and
activity
range
are
defined
to
be
that
by
the
end
of
the
six­
month
period,
the
ranges
of
the
matrices
and
activities
that
were
measured
during
that
period
were
addressed
in
the
interfering
matrix
checks
performed
in
the
same
period
and
are
relative
to
the
range
spanned
in
the
calibration
of
the
system.
It
is
not
required
to
have
performed
an
interfering
matrix
check
for
an
activity
range
or
matrix
that
was
not
analyzed
during
that
sixmonth
period.

Interfering
surrogate
matrix
containers
must
be
constructed
in
such
a
way
that
the
waste
characteristics
do
not
change
over
time
or
are
replaced
before
the
characteristics
significantly
change.

Facility
procedures
shall
define
the
means
to
ensure
the
interfering
matrix
checks
satisfy
the
requirement
to
test
the
range
of
activity
and
matrices
over
a
six­
month
period.

The
applicable
combinations
of
matrices
and
activity
ranges
shall
be
technically
justified
and
documented
in
a
report
to
the
SPO
and
approved
by
the
SQAO.
New
waste
matrices
shall
be
evaluated
as
they
arise.
Minimum
requirements
are:

 
The
uppermost
range
of
activity
must
be
within
the
upper
one­
third
(
1/
3)
of
the
applicable
activity
range
for
the
system,
 
The
lowermost
range
of
activity
must
be
within
the
lower
one­
third
(
1/
3)
of
the
applicable
activity
range
for
the
system,
 
The
matrix
is
defined
based
upon
density
and
the
uppermost
range
shall
be
within
the
upper
one­
third
(
1/
3)
of
the
applicable
density
range
for
the
system,
and
 
The
lowermost
range
of
density
must
be
within
the
lower
one­
third
(
1/
3)
of
the
applicable
density
range
for
the
system.
 
If
the
range
of
activity
and/
or
density
is
relatively
constant
within
the
applicable
six­
month
period
(
i.
e.,
stays
within
the
same
third
of
the
range),
only
a
single
range
is
required
to
be
tested.
For
example,
if
all
measurements
performed
during
the
applicable
period
fall
in
the
lower
one­
third
of
the
calibration
range,
the
activity
used
in
the
interfering
matrix
checks
may
be
limited
to
the
lower
one­
third
of
the
calibration
range.
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For
neutron
systems,
the
matrix
is
characterized
in
terms
of
its
absorption
and
moderation
properties
rather
than
its
physical
density.

The
interfering
matrix
checks
shall
be
reviewed
and
evaluated
at
least
weekly
by
the
cognizant
engineer
or
an
NDA
scientist
to
determine
continued
acceptability
of
the
assay
system
and
to
monitor
for
adverse
trends.
Facility
procedures
shall
define
trend
acceptance
criteria
and
acceptance
criteria
for
interfering
matrix
checks.
At
a
minimum,
the
following
conditions
require
initiation
of
an
NCR
or
CAR
and
investigation:

 
Any
individual
measurement
with
accuracy
(%
R)
not
within
±
60
percent
of
stated
source
activity
at
time
of
measurement,
 
Six
consecutive
measurements
with
the
accuracy
(%
R)
increasing
or
decreasing,
or
 
Indication
of
other
abnormal
trends
or
conditions.

4.
Alternative
Control
Limits:
With
CBFO
approval,
alternative
methodologies
may
be
used
to
establish
control
limits.
The
student
t­
distribution
may
be
used
to
establish
control
limits
for
efficiency.
Nonstatistical
control
limits
may
be
used
for
other
parameters
such
as
energy
and
resolution
provided
they
are
technically
justified.
Facility
procedures
shall
specify
the
methodology
to
establish
these
control
limits.

E.
3.2.3
Evaluation
Criteria
for
Trend
Analysis
1.
Successful
performance
of
the
daily
background
measurements
(
i.
e.,
results
are
within
acceptance
limits)
satisfies
weekly
review
requirements
for
background
measurements.

2.
Trending
Criteria
for
Instrument
Performance
Measurements:
Instrument
performance
measurements
shall
be
reviewed
and
evaluated
at
least
weekly
by
the
cognizant
engineer
or
an
NDA
scientist
to
determine
continued
acceptability
of
the
assay
system
and
to
monitor
for
adverse
trends.
Facility
procedures
shall
define
trend
acceptance
criteria.
At
a
minimum,
if
any
of
the
conditions
below
occur,
the
facility
shall
notify
the
SQAO.
An
investigation
shall
be
performed,
documented,
and
approved
by
the
SQAO
before
resuming
routine
operations.
This
investigation
shall
be
discussed
in
or
attached
to
affected
NDA
batch
reports.

 
For
efficiency,
six
consecutive
measurements
all
increasing
or
decreasing,
 
A
detailed
review
of
the
results
indicates
other
abnormal
trends
or
conditions.

E.
3.2.4
Documenting
Trend
Analysis
and
Weekly
Interfering
Matrix
Checks
Unless
specifically
approved
by
the
SPM,
within
one
month
of
the
close
of
the
six­
month
period,
the
facility
shall
document
the
results
of
the
interfering
matrix
checks
in
a
report
to
the
SPM.
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This
report
shall
include
the
applicable
ranges
and
matrices
of
wastes
measured
during
that
period,
both
for
measurement
of
wastes
and
for
the
weekly
interfering
matrix
checks
that
were
performed.

E.
3.3
NDA
Quality
Control
Requirements
for
Calorimetry
Systems
E.
3.3.1
Recommended
Consensus
Standards
The
assay
procedures
and
related
requirements
and
guidance
cited
in
certain
ASTM
and
ANSI
standards
(
references
E9,
E14,
E15
and
E17)
and
NRC
standard
practices
and
guidelines
(
reference
E16)
as
referenced
in
this
appendix
are
recommended
for
use
at
all
Hanford
facilities.
Since
these
consensus
standards
address
a
multitude
of
operating
systems,
environments,
regulatory
requirements,
etc.,
it
is
not
practical
to
accept
any
of
these
standards
in
their
entirety.

E.
3.3.2
Quality
Control
Requirements
The
information
below
summarizes
the
minimum
QC
requirements
related
to
NDA
using
calorimetry:

1.
Baseline
Measurements:
Basepower
or
baseline
measurements
shall
be
conducted
at
a
frequency
(
typically
weekly)
specified
in
facility
operating
procedures
and
approved
by
CBFO.
Table
E­
4
contains
acceptance
criteria
for
baseline
or
base
power
measurements.

2.
Instrument
Performance
Measurements:
Instrument
performance
measurements
for
calorimetry
shall
be
performed
with
electrical
and/
or
heat
standards
traceable
to
a
nationally
accredited
measurement
program
at
a
frequency
determined
by
each
facility,
consistent
with
reference
E17.
These
requirements
shall
be
specified
in
facility
operating
procedures
and
must
be
approved
by
CBFO.

3.
Acceptance
Criteria:
Individual
basepower
or
baseline
and
instrument
performance
measurements
shall
be
verified
to
be
within
acceptance
limits
before
permitting
any
routine
operations.
Table
E­
4
contains
acceptance
criteria
for
instrument
performance
measurements.
If
the
NDA
system
fails
to
meet
acceptance
criteria,
the
NDA
system
shall
be
removed
from
service
pending
successful
resolution
of
all
necessary
actions,
and
all
assays
performed
since
the
last
acceptable
instrument
performance
measurements
are
suspect,
pending
satisfactory
resolution.
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Table
E­
4
Control
Limits
(
Range
of
Applicability)
for
Base
Power
and
Instrument
Performance
Measurements
on
Calorimeters
Category
Acceptability
Range
Required
Actions
c
Acceptable
|
Result
|
b
 
2 
a
No
action
required.
Warning
2 
a
<
|
Result
|
b
 
3 
a
The
instrument
performance
measurement
may
be
rerun
no
more
than
twice
(
i.
e.,
maximum
of
three
total
measurements).
If
a
repeat
instrument
performance
measurement
results
in
data
within
±
2 ,
the
additional
instrument
performance
measurement
shall
be
documented
and
work
may
continue.
If
the
system
does
not
fall
within
±
2 
after
a
maximum
of
two
reruns
instrument
performance
measurements,
then
the
required
response
for
the
Action
Range
shall
be
followed.
Action
|
Result
|
b
>
3 
a
As
recommended
by
reference
E17
section
8.4.2,
if
an
instrument
performance
measurement
for
wattage
exceeds
3 ,
a
single
confirmatory
measurement
shall
be
performed.
These
actions
shall
also
be
applied
to
basepower
measurements.
 
If
the
result
of
this
confirmatory
measurement
is
 
2 ,
no
further
action
is
required
except
to
document
both
measurements.
 
If
the
result
of
this
confirmatory
instrument
performance
measurement
is
>
2 
but
 
3 ,
the
actions
for
exceeding
the
Warning
Range
shall
continue
with
the
initial
and
confirmatory
instrument
performance
measurements
being
treated
as
two
results
within
the
Warning
Range.
 
Otherwise,
work
shall
stop,
and
the
occurrence
shall
be
documented
as
an
NCR
or
CAR
and
appropriately
dispositioned.
The
calorimeter
shall
be
removed
from
service
pending
successful
resolution
of
all
necessary
actions,
and
all
assays
performed
since
the
last
acceptable
instrument
performance
measurements
are
suspect,
pending
satisfactory
resolution.
If
the
corrective
action
includes
the
adjustment,
maintenance,
repair,
or
replacement
of
any
system
component,
recalibration
or
calibration
verification
is
required
before
returning
the
calorimeter
to
service.
a
The
standard
deviation
(
 )
is
only
based
on
the
reproducibility
of
the
data
check
measurements
themselves.
This
is
not
TMU.
The
standard
deviation
may
be
periodically
updated
to
account
for
changes
in
system
response
over
time.
The
initial
acceptability
range
and
any
subsequent
changes
shall
be
documented
and
transmitted
to
the
SPO.
If
the
standard
deviation
is
not
calculated
as
the
square
root
of
the
variance
as
calculated
from
ANSI
N15.36­
1994
(
Annex
A,
Equation
A.
1),
the
reference
for
the
equation
that
is
used
must
be
provided
to
and
approved
by
CBFO.
b
Absolute
Value
c
If
failure
of
an
instrument
performance
check
is
due
to
a
procedural
noncompliance
(
e.
g.,
incorrect
or
no
source
used),
a
CAR
will
be
issued.
Additional
instrument
performance
measurement(
s)
shall
be
performed
in
accordance
with
procedural
requirements.
If
these
additional
instrument
performance
measurements
meet
the
acceptance
criteria,
NDA
operations
may
continue
while
the
CAR
is
processed.

Basepower
or
baseline
and
instrument
performance
measurements
shall
be
reviewed
and
evaluated
at
least
weekly
by
the
cognizant
engineer
or
an
NDA
scientist
to
determine
continued
acceptability
of
the
calorimetry
system
and
to
monitor
performance
trends.
Facility
procedures
shall
define
trend
acceptance
criteria.
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4.
Isotopic
Systems:
Isotopic
systems
used
solely
in
conjunction
with
calorimetry
shall
meet
the
applicable
QC
requirements
from
subsection
E.
3.2
above.
Facility
operating
procedures
shall
incorporate
the
applicable
instrument
performance
measurement
requirements.
These
instrument
performance
measurements
may
be
performed
independently
of
or
in
conjunction
with
the
instrument
performance
measurements
for
calorimeters.

E.
3.4
NDA
Quality
Control
Requirements
for
IPAN
Systems
E.
3.4.1
Recommended
Consensus
Standards
The
assay
procedures
related
requirements
and
guidance
cited
in
certain
ASTM
and
ANSI
standards
(
references
E12
and
E15)
and
NRC
standard
practices
and
guidelines
(
reference
E16)
as
referenced
in
this
appendix
are
recommended
for
use
at
all
Hanford
facilities.
Since
these
consensus
standards
address
a
multitude
of
operating
systems,
environments,
regulatory
requirements,
etc.,
it
is
not
practical
to
accept
any
of
these
standards
in
their
entirety.

E.
3.4.2
Quality
Control
Requirements
The
information
below
summarizes
the
minimum
QC
requirements
related
to
IPAN
systems:

1.
Background
Measurements:
Must
be
performed
and
recorded
at
least
once
per
operational
day
unless
specific
approval
for
a
less
frequent
period
is
obtained
from
CBFO.
Contributions
to
background
due
to
radiation
from
nearby
radiation
producing
equipment,
standards,
or
wastes
must
be
carefully
controlled.
More
frequent
background
measurements
must
be
performed
if
the
background
will
vary
significantly
within
a
single
day
or
shift.
Background
measurements
are
not
required
when
the
system
is
out
of
service.

Background
measurements
are
normally
performed
before
the
first
use
of
the
system
for
WIPP­
related
measurements
on
a
given
day.
However,
for
measurements
made
during
off­
hours,
the
period
of
validity
of
the
background
measurement
may
carry
over
into
the
next
calendar
day,
but
only
if
the
time
elapsed
from
the
last
background
measurement
is
less
than
24
hours.

Individual
(
i.
e.,
daily
or
more
frequent)
background
measurements
shall
be
evaluated
against
acceptance
limits
established
in
facility
procedures.
Facility
procedures
shall
also
define
the
actions
to
take
if
background
measurements
result
in
data
that
are
outside
the
acceptable
range.

2.
Instrument
Performance
Measurements:
Instrument
performance
measurements
on
operable
systems
must
be
performed
and
recorded
at
least
once
per
operational
day.
Instrument
performance
measurements
shall
include,
but
are
not
limited
to,
efficiency
checks
and
matrix
correction
checks
(
if
applicable).
Instrument
performance
measurements
are
not
required
when
the
system
is
out
of
service.
Both
radioactive
sources
and
surrogate
waste
matrix
containers
(
both
noninterfering
and
interfering)
may
be
used.
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Instrument
performance
measurements
are
normally
performed
before
the
first
use
of
the
system
for
WIPP­
related
measurements
on
a
given
day.
However,
for
measurements
made
during
off­
hours,
the
period
of
validity
of
the
instrument
performance
measurements
may
carry
over
into
the
next
calendar
day,
but
only
if
the
time
elapsed
from
the
last
background
and
instrument
performance
measurement
is
less
than
24
hours.

Individual
(
i.
e.,
daily
or
more
frequent)
instrument
performance
measurements,
regardless
of
whether
or
not
an
interfering
matrix
is
used
for
these
measurements,
shall
be
verified
to
be
within
acceptance
limits
per
table
E­
3
above
before
permitting
any
routine
operations
(
e.
g.,
for
actual
waste
characterization).
If
instrument
performance
measurements
result
in
data
that
are
outside
the
acceptable
range,
the
required
responses
in
table
E­
3
shall
be
followed.

3.
Interfering
Matrix
Checks:
In
addition
to
the
daily
instrument
performance
measurements,
at
least
once
during
the
operational
week,
an
interfering
matrix
must
be
used
to
assess
the
long­
term
stability
of
the
system's
operation
and
matrix
correction.
Surrogate
waste
containers
must
reflect
the
type
of
waste
(
e.
g.,
debris,
sludge)
currently
being
assayed.
Radioactive
standards
and
interfering
matrices
must
be
selected
such
that
over
a
six­
month
period
the
operating
range
of
the
assay
system
is
tested
in
each
applicable
surrogate
waste
matrix.

An
applicable
activity
range
is
defined
to
be
that
by
the
end
of
the
six­
month
period,
the
ranges
and
activities
that
were
measured
during
that
period
were
addressed
in
the
interfering
matrix
checks
performed
in
the
same
period
and
are
relative
to
the
range
spanned
in
the
calibration
of
the
system.
It
is
not
required
to
have
performed
an
interfering
matrix
check
for
an
activity
range
or
matrix
that
was
not
analyzed
during
that
six­
month
period.

Interfering
surrogate
matrix
containers
must
be
constructed
in
such
a
way
that
the
waste
characteristics
do
not
change
over
time
or
are
replaced
before
the
characteristics
significantly
change.

Facility
procedures
shall
define
the
means
to
ensure
the
interfering
matrix
checks
satisfy
the
requirement
to
test
the
range
of
activity
and
matrices
over
a
six­
month
period.

The
applicable
combinations
of
matrices
and
activity
ranges
shall
be
technically
justified
and
documented
in
a
report
to
the
SPO
and
approved
by
the
SQAO.
Minimum
requirements
are:

 
The
uppermost
range
of
activity
must
be
within
the
upper
one­
third
(
1/
3)
of
the
applicable
activity
range
for
the
system,
 
The
lowermost
range
of
activity
must
be
within
the
lower
one­
third
(
1/
3)
of
the
applicable
activity
range
for
the
system,
and
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If
the
range
of
activity
is
relatively
constant
within
the
applicable
sixmonth
period
(
i.
e.,
stays
within
the
same
third
of
the
range),
only
a
single
range
is
required
to
be
tested.
For
example,
if
all
measurements
performed
during
the
applicable
period
fall
in
the
lower
one­
third
of
the
calibration
range,
the
activity
used
in
the
interfering
matrix
checks
may
be
limited
to
the
lower
one­
third
of
the
calibration
range.

The
interfering
matrix
checks
shall
be
reviewed
and
evaluated
at
least
weekly
by
the
cognizant
engineer
or
an
NDA
scientist
to
determine
continued
acceptability
of
the
assay
system
and
to
monitor
for
adverse
trends.
Facility
procedures
shall
define
trend
acceptance
criteria
and
acceptance
criteria
for
interfering
matrix
checks.
At
a
minimum,
the
following
conditions
require
initiation
of
an
NCR
or
CAR
and
investigation:

 
Any
individual
measurement
with
accuracy
(%
R)
not
within
±
60
percent
of
stated
source
activity
at
time
of
measurement,
 
Six
consecutive
measurements
with
the
accuracy
(%
R)
increasing
or
decreasing,
or
 
A
detailed
review
of
the
results
indicates
other
abnormal
trends
or
conditions.

E.
3.4.3
Evaluation
Criteria
for
Trend
Analysis
4.
Successful
performance
of
the
daily
background
measurements
(
i.
e.,
results
are
within
acceptance
limits)
satisfies
weekly
review
requirements
for
background
measurements.

5.
Trending
Criteria
for
Instrument
Performance
Measurements:
Instrument
performance
measurements
shall
be
reviewed
and
evaluated
at
least
weekly
by
the
cognizant
engineer
or
an
NDA
scientist
to
determine
continued
acceptability
of
the
assay
system
and
to
monitor
for
adverse
trends.
Facility
procedures
shall
define
trend
acceptance
criteria.
At
a
minimum,
if
any
of
the
conditions
below
occur,
the
facility
shall
notify
the
SQAO.
An
investigation
shall
be
performed,
documented,
and
approved
by
SQAO
before
resuming
routine
operations.
This
investigation
shall
be
discussed
in
or
attached
to
affected
NDA
batch
reports.

 
Six
consecutive
measurements
all
increasing
or
decreasing,
or
 
A
detailed
review
of
the
results
indicates
other
abnormal
trends
or
conditions.

E.
3.4.4
Documenting
Trend
Analysis
Unless
specifically
approved
by
the
SPM,
within
one
month
of
the
close
of
the
six­
month
period,
the
facility
shall
document
the
results
of
the
interfering
matrix
checks
in
a
report
to
the
SPM.
This
report
shall
include
the
applicable
ranges
and
matrices
of
wastes
measured
during
that
HNF­
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period,
both
for
measurement
of
wastes
and
for
the
weekly
interfering
matrix
checks
that
were
performed.

E.
3.5
NDA
Quality
Control
Requirements
for
SuperHENC
Systems
E.
3.5.1
Recommended
Consensus
Standards
The
assay
procedures
related
requirements
and
guidance
cited
in
certain
ASTM
and
ANSI
standards
(
references
E15
and
E33)
and
NRC
standard
practices
and
guidelines
(
reference
E16)
as
referenced
in
this
appendix
are
recommended
for
use
at
all
Hanford
facilities.
Since
these
consensus
standards
address
a
multitude
of
operating
systems,
environments,
regulatory
requirements,
etc.,
it
is
not
practical
to
accept
any
of
these
standards
in
their
entirety.

E.
3.5.2
Quality
Control
Requirements
The
information
below
summarizes
the
minimum
QC
requirements
related
to
SuperHENC
systems:

1.
Background
Measurements:
Must
be
performed
and
recorded
at
least
once
per
operational
day
unless
specific
approval
for
a
less
frequent
period
is
obtained
from
CBFO.
Contributions
to
background
due
to
radiation
from
nearby
radiation
producing
equipment,
standards,
or
wastes
must
be
carefully
controlled.
More
frequent
background
measurements
must
be
performed
if
the
background
will
vary
significantly
within
a
single
day
or
shift.
Background
measurements
are
not
required
when
the
system
is
out
of
service.

Background
measurements
are
normally
performed
before
the
first
use
of
the
system
for
WIPP­
related
measurements
on
a
given
day.
However,
for
measurements
made
during
off­
hours,
the
period
of
validity
of
the
background
measurement
may
carry
over
into
the
next
calendar
day,
but
only
if
the
time
elapsed
from
the
last
background
measurement
is
less
than
24
hours.

Individual
(
i.
e.,
daily
or
more
frequent)
background
measurements
shall
be
evaluated
against
acceptance
limits
established
in
facility
procedures.
Facility
procedures
shall
also
define
the
actions
to
take
if
background
measurements
result
in
data
that
are
outside
the
acceptable
range.

2.
Instrument
Performance
Measurements:
Instrument
performance
measurements
on
operable
systems
must
be
performed
and
recorded
at
least
once
per
operational
day.
Instrument
performance
measurements
shall
include,
but
are
not
limited
to,
efficiency
checks
and
matrix
correction
checks.
Instrument
performance
measurements
are
not
required
when
the
system
is
out
of
service.
Both
radioactive
sources
and
surrogate
waste
matrix
containers
(
both
non­
interfering
and
interfering)
are
used.
The
interfering
matrix
checks
are
discussed
in
E.
3.5.2(
3)
below.
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Instrument
performance
measurements
are
normally
performed
before
the
first
use
of
the
system
for
WIPP­
related
measurements
on
a
given
day.
However,
for
measurements
made
during
off­
hours,
the
period
of
validity
of
the
instrument
performance
measurements
may
carry
over
into
the
next
calendar
day,
but
only
if
the
time
elapsed
from
the
last
background
and
instrument
performance
measurement
is
less
than
24
hours.

Individual
(
i.
e.,
daily
or
more
frequent)
instrument
performance
measurements,
regardless
of
whether
or
not
an
interfering
matrix
is
used
for
these
measurements,
shall
be
verified
to
be
within
acceptance
limits
per
table
E­
3
above
before
permitting
any
routine
operations
(
e.
g.,
for
actual
waste
characterization).
If
instrument
performance
measurements
result
in
data
that
are
outside
the
acceptable
range,
the
required
responses
in
table
E­
3
shall
be
followed.

3.
Interfering
Matrix
Checks:
In
addition
to
the
daily
instrument
performance
measurements,
at
least
once
during
the
operational
week,
an
interfering
matrix
must
be
used
to
assess
the
long­
term
stability
of
the
system's
operation
and
matrix
correction.
Surrogate
waste
containers
must
reflect
the
type
of
waste
(
e.
g.,
debris,
sludge)
currently
being
assayed.
Radioactive
standards
and
interfering
matrices
must
be
selected
such
that
over
a
six­
month
period
the
operating
range
of
the
assay
system
is
tested
in
each
applicable
surrogate
waste
matrix.

An
applicable
activity
range
is
defined
to
be
that
by
the
end
of
the
six­
month
period,
the
ranges
and
activities
that
were
measured
during
that
period
were
addressed
in
the
interfering
matrix
checks
performed
in
the
same
period
and
are
relative
to
the
range
spanned
in
the
calibration
of
the
system.
It
is
not
required
to
have
performed
an
interfering
matrix
check
for
an
activity
range
or
matrix
that
was
not
analyzed
during
that
six­
month
period.

Interfering
surrogate
matrix
containers
must
be
constructed
in
such
a
way
that
the
waste
characteristics
do
not
change
over
time
or
are
replaced
before
the
characteristics
significantly
change.

Facility
procedures
shall
define
the
means
to
ensure
the
interfering
matrix
checks
satisfy
the
requirement
to
test
the
range
of
activity
and
matrices
over
a
six­
month
period.

The
applicable
combinations
of
matrices
and
activity
ranges
shall
be
technically
justified
and
documented
in
a
report
to
the
SPO
and
approved
by
the
SQAO.
Minimum
requirements
are:

 
The
uppermost
range
of
activity
must
be
within
the
upper
one­
third
(
1/
3)
of
the
applicable
activity
range
for
the
system,
 
The
lowermost
range
of
activity
must
be
within
the
lower
one­
third
(
1/
3)
of
the
applicable
activity
range
for
the
system,
and
HNF­
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SITE
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PLAN
 
If
the
range
of
activity
is
relatively
constant
within
the
applicable
sixmonth
period
(
i.
e.,
stays
within
the
same
third
of
the
range),
only
a
single
range
is
required
to
be
tested.
For
example,
if
all
measurements
performed
during
the
applicable
period
fall
in
the
lower
one­
third
of
the
calibration
range,
the
activity
used
in
the
interfering
matrix
checks
may
be
limited
to
the
lower
one­
third
of
the
calibration
range.

The
interfering
matrix
checks
shall
be
reviewed
and
evaluated
at
least
weekly
by
the
cognizant
engineer
or
an
NDA
scientist
to
determine
continued
acceptability
of
the
assay
system
and
to
monitor
for
adverse
trends.
Facility
procedures
shall
define
trend
acceptance
criteria
and
acceptance
criteria
for
interfering
matrix
checks.
At
a
minimum,
the
following
conditions
require
initiation
of
an
NCR
or
CAR
and
investigation:

 
Any
individual
measurement
with
accuracy
(%
R)
not
within
±
60
percent
of
stated
source
activity
at
time
of
measurement,
 
Six
consecutive
measurements
with
the
accuracy
(%
R)
increasing
or
decreasing,
or
 
A
detailed
review
of
the
results
indicates
other
abnormal
trends
or
conditions.

E.
3.5.3
Evaluation
Criteria
for
Trend
Analysis
1.
Successful
performance
of
the
daily
background
measurements
(
i.
e.,
results
are
within
acceptance
limits)
satisfies
weekly
review
requirements
for
background
measurements.

2.
Trending
Criteria
for
Instrument
Performance
Measurements:
Instrument
performance
measurements
shall
be
reviewed
and
evaluated
at
least
weekly
by
the
cognizant
engineer
or
an
NDA
scientist
to
determine
continued
acceptability
of
the
assay
system
and
to
monitor
for
adverse
trends.
Facility
procedures
shall
define
trend
acceptance
criteria.
At
a
minimum,
if
any
of
the
conditions
below
occur,
the
facility
shall
notify
the
SQAO.
An
investigation
shall
be
performed,
documented,
and
approved
by
SQAO
before
resuming
routine
operations.
This
investigation
shall
be
discussed
in
or
attached
to
affected
NDA
batch
reports.

 
Six
consecutive
measurements
all
increasing
or
decreasing,
or
 
A
detailed
review
of
the
results
indicates
other
abnormal
trends
or
conditions.

E.
3.5.4
Documenting
Trend
Analysis
Unless
specifically
approved
by
the
SPM,
within
one
month
of
the
close
of
the
six­
month
period,
the
facility
shall
document
the
results
of
the
interfering
matrix
checks
in
a
report
to
the
SPM.
This
report
shall
include
the
applicable
ranges
and
matrices
of
wastes
measured
during
that
HNF­
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260
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HANFORD
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TRANSURANIC
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CERTIFICATION
PLAN
period,
both
for
measurement
of
wastes
and
for
the
weekly
interfering
matrix
checks
that
were
performed.

E.
4
DATA
MANAGEMENT
E.
4.1
Data
Review
and
Validation
All
NDA
data
must
be
reviewed
and
approved
by
qualified
personnel
before
being
reported.
At
a
minimum,
the
data
must
be
reviewed
by
an
independent
technical
reviewer,
SQAO,
and
approved
by
the
SPM.
The
validation
process
includes
verification
that
the
applicable
quality
controls
specified
in
subsection
E.
3
have
been
met.

Facility
procedures
shall
specify
the
exact
requirements
for
data
validation,
verification
and
review
by
an
independent
technical
reviewer
(
ITR).

In
general,
the
requirements
of
section
B3­
10
of
reference
E21
shall
be
incorporated
into
the
review
requirements
and
combines
the
requirements
for
data­
generation
level,
independent
technical
review
(
ITR),
and
technical
supervisor
review.
Key
issues
to
be
reviewed
include,
but
are
not
limited
to:

 
ITR
review
shall
be
documented
in
a
checklist
format,
 
Data
generation
and
reduction
have
been
performed
in
accordance
with
procedural
requirements,
 
Verification
of
calculations
or
data
entry
as
appropriate,
 
Instrument
performance
and
background
measurements
for
the
affected
period
have
been
performed,
documented,
and
meet
acceptance
criteria
and
have
been
evaluated
for
adverse
trends.
Appropriate
corrective
actions
have
been
documented
and
successfully
completed,
 
Batch
data
report
is
otherwise
assembled
and
complete
in
accordance
with
facility
procedures,
 
Data
is
technically
correct
and
justified.
All
anomalies,
error
messages,
warning
flags,
etc.,
have
been
corrected
or
justified
in
the
report,
 
Analytical
measurements
are
performed
within
any
limits
for
activity,
waste
matrix,
calibration
range,
etc.,
 
Report
is
complete
(
through
ITR)
and
data
properly
reported.

The
ITR
of
NDA
data
for
use
in
batch
data
reports
is
defined
to
be
a
person
qualified
to
perform
the
work
as
NDA
scientist
(
analyst)
who
has
not
acted
in
the
capacity
of
data
analyst
for
any
of
the
waste
analyses
contained
in
the
affected
NDA
batch
data
report.

SPO
procedures
shall
specify
the
review
requirements
for
review,
validation,
and
verification
by
SQAO.
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In
general,
the
requirements
of
section
B3­
10
of
reference
E21
shall
be
incorporated
into
the
procedural
requirements
and
combine
the
requirements
for
QA
officer
review
and
SQAO
review.
Key
issues
to
be
reviewed
or
incorporated
include,
but
are
not
limited
to:

 
SQAO
review
shall
be
documented
in
a
checklist
format,
 
ITR
review
complete
with
any
open
issues
satisfactorily
resolved,
 
Background
and
instrument
performance
measurements
for
the
applicable
period
are
attached
and
meet
acceptance
criteria,
including
any
trends,
 
Analytical
measurements
are
performed
within
any
limits
for
activity,
waste
matrix,
calibration
range,
etc.,
 
Copies
of
any
CAR
or
NCR
affecting
the
data
within
the
batch
are
attached,
 
Report
is
complete
and
data
properly
reported,
and,
 
Any
person
qualified
as
SQAO
may
perform
the
SQAO
review
of
an
NDA
batch
data
report.

SPM
Approval:

 
Any
person
qualified
as
SPM
may
perform
the
SPM
approval
of
an
NDA
batch
data
report,
 
SPM
approval
demonstrates
the
ITR
and
SQAO
reviews
have
been
successfully
completed
with
any
and
all
problems
or
issues
satisfactorily
resolved
and
the
associated
checklists
are
complete,
 
Verifies
the
data
is
now
acceptable
to
permit
shipment
to
WIPP,
and
 
A
checklist
is
not
required,
although
SPM
signature
and
date
is
required,
when
approved.

E.
4.2
Data
Reporting
E.
4.2.1
NDA
Batch
Data
Reports
NDA
data
must
be
reported
to
the
SPO
on
a
batch
basis.
For
the
purpose
of
the
Hanford
TRU
Project,
batches
are
defined
as
a
suite
of
waste
containers
undergoing
NDA
using
the
same
system
or
equipment.
A
single
batch
report
is
limited
to
20
waste
containers
excepting
that
the
SPM
may
authorize
a
greater
number
on
a
case­
by­
case
basis
for
batches
assayed
on
or
after
May
17,
2002.

Each
facility
is
required
to
submit
batch
data
reports
for
each
batch
to
the
SPO
on
standard
forms
(
either
hard
copy
or
electronic
equivalent),
as
provided
in
approved
facility
procedures.
NDA
batch
data
reports
shall
consist
of
the
following:

 
Facility
name,
batch
number,
container
numbers
included
in
that
batch
 
Table
of
contents
 
Narrative
or
executive
summary,
including
any
explanation
of
issues
or
problems
associated
with
the
batch
 
Background
and
instrument
performance
measurement
data
or
control
charts
for
the
relevant
time
period
(
i.
e.,
at
least
the
duration
over
which
the
containers
in
that
batch
were
assayed)
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HANFORD
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Any
NCR
or
CAR
directly
associated
with
NDA
for
that
batch
 
For
all
NDA
batch
data
reports
with
data
collected
before
May
17,
2002,
a
statement
that
the
data
was
collected
before
May
17,
2002
(
or
effective
date
of
CH­
WAC,
reference
E20)
and
the
replicate
analysis
are
substituted
for
the
weekly
interfering
matrix
checks
 
Identification
of
or
reference
to
applicable
calibration,
TMU,
and
QAO
reports
(
QAO
report
applies
to
measurements
performed
but
not
validated
before
May
17,
2002)
 
Signed
ITR
and
SQAO
data
validation
checklists
in
accordance
with
reference
E2
(
QAPD,
section
5.3.2),
applicable
facility
procedures,
and
reference
E26
 
Separate
report
sheet(
s)
for
each
container
in
the
batch
that
include,
but
are
not
limited
to:

1.
Title
of
"
Radioassay
Data
Sheet"

2.
Method
used
for
NDA
(
i.
e.,
procedure
identification)

3.
Date
of
NDA
4.
For
batches
with
measurements
obtained
before
May
17,
2002:

a.
Positive
identification
of
each
replicate
analysis
b.
Positive
indication
of
whether
or
not
the
replicate
analysis
met
the
acceptance
criteria
5.
Activities
and/
or
masses
of
individual
radioisotopes
present,
the
associated
TMUs
and
the
confidence
level
for
which
the
TMU
was
calculated
(
curies
and/
or
grams).
For
the
ten
WIPP­
tracked
isotopes
results
less
than
LLD
shall
be
reported
as
"<
LLD"
(
zero
shall
be
used
if
the
isotope
is
documented
in
AK
as
not
being
present
in
the
container)

6.
Signature/
date
of
both
analyst
and
reviewer
7.
Other
information
or
radiological
properties
shall
be
documented
on
the
radioassay
data
sheet
including,
but
not
limited
to:

a.
Decay
heat
expressed
in
watts
(
W)
and
its
associated
TMU
b.
Total
239Pu
FGE
expressed
in
grams
(
g)
and
its
associated
TMU
c.
TRU
alpha
activity
concentration
expressed
in
curies/
gram
(
Ci/
g)
and
associated
TMU
­;
further
TRU
alpha
activity
is
defined
to
be
the
sum
of
the
activities
of
TRU
isotopes
that
decay
by
alpha
emission
and
have
halflives
greater
than
20
years
d.
Total
239Pu
equivalent
activity
expressed
in
curies
(
PE­
Ci)

8.
Reported
analytical
results
or
summaries
including
signatures/
dates
of
operator
and
analyst/
reviewer
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9.
Sufficient
information
to
permit
the
independent
calculation
of
the
activity
of
radionuclides
that
are
scaled
or
correlated
from
the
measured
values
for
other
radionuclides
(
e.
g.,
90Sr
calculated
from
measured
137Cs
or
234U
from
235U
or
238U)

10.
Radionuclides
that
are
neither
one
of
the
ten
WIPP­
tracked
isotopes
nor
otherwise
contribute
to
95
percent
of
the
total
radiological
hazard
must
have
their
activity/
mass
reported
if
either
of
the
below
conditions
are
met.
Reporting
may
be
either
on
the
radioassay
data
sheet
or
elsewhere
within
the
report:

a.
The
radionuclide
contributes
to
FGE
or
decay
heat
(
e.
g.,
241Pu,
237Np
or
235U)

b.
The
radionuclide
is
used
to
scale
one
of
the
ten
WIPP­
tracked
isotopes.

11.
Signature
approval
and
release
by
SPM.

E.
4.2.2
Calibration
Reports
Calibration
and
recalibration
reports
prepared
on
or
after
May
17,
2002,
shall
include,
but
are
not
limited
to,
the
following:

 
System
description,
including
modifications,
major
repairs,
replacement
of
major
components,
etc.,
since
last
report
 
Range
of
operation
for
which
the
calibration
is
valid
(
both
activity
and
matrices)
 
Description
of
calibration
methodology
 
Period
for
which
calibration
is
applicable
 
Summary
and
description
of
the
calibration
confirmation
 
Results
of
calibration
confirmation
 
Reports
of
all
calibration
parameters,
components,
functions
calibrated
 
Supporting
analytical
results
 
System
settings,
operating
parameters,
etc.
 
Must
be
reviewed
and
approved
by
the
SQAO.

E.
4.2.3
Total
Measurement
Uncertainty
Reports
TMU
reports
prepared
on
or
after
May
17,
2002,
shall
include,
but
are
not
limited
to,
the
following
requirements:

 
Description
of
system(
s),
including
modifications,
major
repairs,
replacement
of
major
components,
etc.,
since
last
report
 
Identification
of
and
technical
justification
for
like
or
similar
systems
 
Assumptions,
limits,
range,
matrices,
etc.,
to
which
the
TMU
is
applicable
 
Evaluation
of
the
individual
contributing
components
to
TMU
 
Total
measurement
uncertainty
and
equations
for
individual
isotopes
and
parameters
in
accordance
with
reference
E6
 
Must
be
reviewed
and
approved
by
the
SQAO.
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E.
4.2.4
Calibration
Verification
Reports
Calibration
verification
reports
prepared
on
or
after
May
17,
2002,
shall
include,
but
are
not
limited
to,
the
following:

 
System
description,
including
modifications,
major
repairs,
replacement
of
major
components,
etc.,
since
last
calibration
or
calibration
verification
report
 
Range
of
operation
for
which
the
calibration
is
valid
(
both
activity
and
matrices)
 
Period
for
which
calibration
is
applicable
 
Summary
and
description
of
the
calibration
verification
 
Results
of
calibration
verification
 
Supporting
analytical
results
 
Must
be
reviewed
and
approved
by
the
SQAO.
 
Technical
justification
must
also
be
included
if
only
partial
calibration
verification
is
performed
(
e.
g.,
calibration
verification
does
not
test
all
concurrent
calibrations
or
does
not
test
the
full
system).

E.
4.3
Data
and
Records
Retention
The
following
records
shall
be
forwarded
to
the
SPO
and
shall
be
documented
and
retrievable
by
NDA
batch
number,
in
accordance
with
reference
E2
(
QAPD):

 
NDA
batch
reports
 
All
raw
data,
including
instrument
readouts,
calculation
records,
and
NDA
QC
results
(
both
background
or
power
baseline
and
instrument
performance
measurements).
Raw
data
includes,
but
is
not
limited
to,
the
original
data
collected
for
subsequent
analysis
 
All
instrument
calibration
reports,
including
the
analysis
of
the
associated
standards
and
any
confirmatory
measurements
performed
to
satisfy
the
calibration
confirmation
requirements.
"
Calibration
reports"
include
the
original
analytical
results
collected
to
perform
any
and
all
portions
of
the
calibration
(
e.
g.,
energy
calibration,
efficiency
determination,
system
correction
factor
determination,
calibration
confirmation,
etc.).
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E.
4.4
Required
Reports
Table
E­
5
summarizes
routinely
generated
reports
required
by
this
appendix.
This
list
cannot
be
all
inclusive
and
does
not
address
special
occurrences.

Table
E­
5
Summary
of
Required
Reports
Report
Subject
Frequency
Comments
Reference
Section
NDA
Batch
Data
Reports
As
generated
AK
Summary
Report
As
generated,
updated
as
necessary
As
related
to
radionuclides
present
and
their
fractional
abundances
E.
2.2.1
E.
2.2.2
Acceptable
Knowledge
Source
Document
Deficiency
As
generated
E.
2.2.3
Method
to
Quantify
234U
and
90Sr
As
generated
May
need
to
update
this
on
a
waste
stream
basis
E.
2.1
Calibration
Report
Following
initial
calibration
Calibration
confirmation
also
required
E.
3
E.
5.2.2
Recalibration
Report
After
each
recalibration
Calibration
confirmation
also
required
E.
3
E.
5.2.2
Calibration
Confirmation
Concurrent
with
each
calibration
or
recalibration
May
be
documented
separately
or
included
in
calibration
report
E.
3
Calibration
Verification
As
performed
(
following
system
repair,
modification,
etc.)
E.
3
E.
5.2.4
LLD
Methodology
As
generated,
updated
as
necessary
Must
include
equivalent
LLD
for
isotopes
that
cannot
be
measured
(
e.
g.,
90Sr
and
234U)
E.
3
TMU
Report
As
generated,
updated
as
necessary
Must
be
submitted
to
CBFO
E.
3
E.
5.2.3
Methodology
for
Alternate
Control
Limits
As
needed
Must
be
approved
by
CBFO
before
implementation
of
methodology
E.
4.2.2
E.
4.4.2
CAR/
NCR
As
generated
Various
Interfering
Matrix
Checks
and
Trend
Analysis
1
month
after
end
of
6­
month
period
E.
4.2.2
E.
4.3.2
E.
4.4.2
Correlation
of
Sources
to
Primary
Standards
When
performed
E.
3
Calibration
Technique
If
not
performed
in
accordance
with
consensus
standards
Requires
pre­
approval
by
CBFO
E.
3
Alternate
Calibration
Confirmation
Accuracy
and
Precision
Limits
As
needed
Requires
pre­
approval
by
CBFO
E.
3
Calorimetry
Baseline
and
Instrument
Performance
Measurement
Frequency
Prior
to
use
and
whenever
updated
Requires
pre­
approval
by
CBFO
and
must
include
equivalent
trending
E.
4.3.2
Definition
of
applicable
operating
ranges
for
weekly
interfering
matrix
checks
Prior
to
use
and
whenever
updated
E.
4.2.2
E.
4.3.2
E.
4.4.2
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E.
5
QUALITY
CHARACTERISTICS
ASSESSMENT
Per
40
CFR
§
194.22(
c),
there
are
five
"
quality
characteristics"
that
have
to
be
assessed.
These
quality
characteristics
and
the
method
by
which
they
are
assessed
are
described
in
the
following
sections.

E.
5.1
Data
Accuracy
Per
40
CFR
§
194.22(
c)(
1),
Data
Accuracy
is
defined
as
"
the
degree
to
which
data
agree
with
an
acceptable
reference
or
true
value."
For
NDA
methods,
this
quality
characteristic
is
met
and
maintained
as
described
in
subsection
E.
2.

E.
5.2
Data
Precision
Per
40
CFR
§
194.22(
c)(
2),
Data
Precision
is
defined
as
"
a
measure
of
the
mutual
agreement
between
comparable
data
gathered
or
developed
under
similar
conditions
expressed
in
terms
of
standard
deviation."
For
NDA
methods,
this
quality
characteristic
is
met
and
maintained
as
described
in
subsection
E.
2.

E.
5.3
Data
Representativeness
Per
40
CFR
§
194.22(
c)(
3),
Data
Representativeness
is
defined
as
"
the
degree
to
which
data
can
accurately
and
precisely
represent
a
characteristic
of
a
population,
a
parameter,
variations
at
a
sampling
point,
or
environmental
conditions."
For
NDA
this
quality
characteristic
for
the
waste
stream
is
met
and
maintained
through
100
percent
measurement
confirmation
on
a
payload
container
basis.

E.
5.4
Data
Completeness
Per
40
CFR
§
194.22(
c)(
4),
Data
Completeness
is
defined
as
"
a
measure
of
the
amount
of
valid
data
obtained
compared
to
the
amount
that
was
expected."
For
NDA
methods,
this
quality
characteristic
is
met
and
maintained
by
requiring
100
percent
valid
results.
Any
result
indicating
the
NDA
measurement
was
invalid
requires
re­
measurement.

E.
5.5
Data
Comparability
Per
40
CFR
§
194.22(
c)(
5),
Data
Comparability
is
defined
as
"
a
measure
of
confidence
with
which
one
data
set
can
be
compared
to
another."
For
NDA
this
quality
characteristic
is
addressed
by
ensuring
that
all
data
are
produced
under
the
same
system
of
controls.
These
controls
apply
to
all
aspects
of
the
data­
generation
process,
including
procurement
of
analytical
instruments;
calibration
and
operation
of
assay
equipment
according
to
industry
standards;
preparation
and
use
of
standardized
instrument
and
data
review
procedures;
and
training
of
equipment
operators
and
technical/
data
review
personnel
to
the
QAPD,
as
specified
in
subsection
E.
3.1.
Additionally,
comparison
of
measured
data
with
AK­
derived
or
based
values,
as
applicable,
provides
a
means
to
assess
comparability
on
a
waste
stream
basis.
Although
no
specific
confidence
level
is
specified,
these
controls
provide
comparability
among
all
data
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generated
under
this
program.
Sites
using
NDA
systems
shall
participate
in
measurement
comparison
programs
as
specified
in
subsection
E.
3.1.

E.
6
239PU
EQUIVALENT
ACTIVITY
239Pu
equivalent
activity
(
PE­
Ci)
is
calculated
and
reported
for
each
container
of
TRU
waste.
This
calculation
normalizes
the
activity
for
each
TRU
isotope
to
that
of
239Pu.
PE­
Ci
is
calculated
for
each
and
every
TRU
isotope
regardless
of
half­
life
(
t1/
2)
or
method
of
decay
and
for
233U
using
the
following
formula:

 =
=
 
k
i
i
i
WF
A
Ci
PE
1
where:
k
 
the
number
of
TRU
isotopes
including
233U
(
without
regard
to
method
of
decay
or
t1/
2)
Ai
 
the
activity
(
in
Curies)
of
TRU
radionuclide
i
WFi
 
the
weight
factor
(
WF)
for
TRU
radionuclide
i
WF
is
defined
to
be
the
ratio
of
the
50­
year
effective
whole­
body
dose
commitment
due
to
the
inhalation
of
239Pu
particulates
with
a
1.0
µ
m
activity
median
aerodynamic
diameter
(
AMAD)
and
a
weekly
pulmonary
clearance
class
(
CEDEPu­
239)
to
the
50­
year
effective
whole­
body
dose
commitment
due
to
the
inhalation
of
radionuclide
i
particulates,
with
a
1.0
µ
m
activity
median
aerodynamic
diameter
and
the
pulmonary
clearance
class
resulting
in
the
highest
50­
year
effective
whole­
body
dose
commitment
(
CEDEi).
The
values
of
CEDEPu­
239
and
CEDEi
are
taken
from
DOE/
EH­
0071
(
reference
E18).
Mathematically,
this
is
expressed
as:

i
Pu
i
CEDE
CEDE
WF
239
 
=

Table
E­
6
contains
the
weighting
factors
for
TRU
isotopes
listed
in
reference
E18,
section
1.3.7,
that
have
a
50­
year
committed
dose
equivalent
factor
(
Ei
as
used
in
reference
E20,
CEDE
as
used
on
reference
E19)
identified
in
reference
E19.
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Table
E­
6
PE­
Ci
Weighting
Factors
Isotope
Atomic
No.
Class
CEDE
WF
1
/
WF
Comment
U­
233
92
Y
1.30E+
02
3.9
0.3
Np­
237
93
W
4.90E+
02
1.0
1.0
Pu­
236
94
W
1.60E+
02
3.2
0.3
Pu­
238
94
W
4.60E+
02
1.1
0.9
Pu­
239
94
W
5.10E+
02
1.0
1.0
Pu­
240
94
W
5.10E+
02
1.0
1.0
Pu­
241
94
W
1.00E+
01
51.0
0.0
Pu­
242
94
W
4.80E+
02
1.1
0.9
Pu­
244
94
W
4.80E+
02
1.1
0.9
Am­
241
95
W
5.20E+
02
1.0
1.0
Am­
242m
95
W
5.10E+
02
1.0
1.0
Am­
243
95
W
5.20E+
02
1.0
1.0
Cm­
242
96
W
1.70E+
01
30.0
0.0
Cm­
243
96
W
3.50E+
02
1.5
0.7
Cm­
244
96
W
2.70E+
02
1.9
0.5
Cm­
245
96
W
5.40E+
02
0.9
1.1
Cm­
246
96
W
5.40E+
02
0.9
1.1
Cm­
247
96
W
4.90E+
02
1.0
1.0
Cm­
248
96
W
1.90E+
03
0.3
3.7
Cm­
250
96
N/
A
N/
A
N/
A
N/
A
Not
Listed
in
DOE/
EH­
0071
Bk­
250
97
W
6.90E­
03
73913.0
0.0
Use
with
caution:
may
be
a
typo
in
DOE/
EH­
0071
Cf­
249
98
W
5.50E+
02
0.9
1.1
Cf­
250
98
W
2.20E+
02
2.3
0.4
Cf­
251
98
W
5.60E+
02
0.9
1.1
Cf­
252
98
Y
1.30E+
02
3.9
0.3
Es­
254
99
W
3.60E+
01
14.2
0.1
E.
7
NDA­
RELATED
PROCEDURES
Table
E­
7
identifies
procedures
used
specifically
for
or
in
the
performance
or
documentation
of
NDA
in
the
Hanford
TRU
Project.
These
procedures
may
also
contain
requirements
for
other
aspects
of
the
Hanford
TRU
Project.
HNF­
2600,
REV
15
Page
269
of
281
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11/
2005
HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
Table
E­
7
NDA
Implementing
Procedures
in
the
Hanford
TRU
Project
Document
number
Title
WMP­
400,
Section
1.2.1
TRU
Training
and
Qualification
Plan
WMP­
400,
Section
1.2.2
Qualification
of
NDA,
NDE,
Visual
Examination,
Transportation,
and
Inspection
and
Test
Personnel
WMP­
400,
Section
1.3.2
TRU
Nonconforming
Item
Reporting
and
Control
WMP­
400,
Section
1.3.3
TRU
Corrective
Action
Reporting
and
Control
WMP­
400,
Section
1.5.1
TRU
Records
Management
WMP­
400,
Section
3.1.2
Quality
Assurance
Reports
to
Management
WMP­
400,
Section
6.1.1
TRU
Software
Quality
Assurance
WMP­
350,
Section
2.2
Calculation
of
Assay
Results
WMP­
350,
Section
2.3
Data
Management
WMP­
350,
Section
2.5
GEA
Energy
and
Efficiency
Setup
and
Baseline
Establishment
WMP­
350,
Section
2.8
WRAP
NDA
Measurement
Control
Program
WMP­
350,
Section
2.9
Performing
Calibration
Verifications
and
Confirmations
for
NDA
at
WRAP
WMP­
350,
Section
2.10
GEA
Calibration
Using
NDA2000
WRP1­
OP­
0905
Imaging
Passive/
Active
Neutron
Assay
Operation
WRP1­
OP­
0906
Gamma
Energy
Assay
Operations
WRP1­
OP­
0907
Gamma
Energy
Assay
Operations
Using
NDA2000
TRU­
OP­
002
Operation
of
the
SuperHENC
Assay
System
ZA­
948­
392
NDA
Using
NDA
2000
ZA­
948­
393
NDA
Using
the
Room
172
ANTECH
Calorimeters
ZA­
400­
303
Energy
and
Efficiency
Setup
and
Baseline
Determination
Using
NDA
2000
HNF­
2600,
REV
15
Page
270
of
281
5/
11/
2005
HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
Table
E­
7
NDA
Implementing
Procedures
in
the
Hanford
TRU
Project
Document
number
Title
ZA­
400­
304
ANTECH
Calorimeter
Calibration
ZA­
400­
302
Calculation
of
Assay
Results
FSP­
PFP­
5­
8,
Section
16.2
Data
Management
FSP­
PFP­
5­
8,
Section
16.3
QC
Criteria
for
Residues
Project
NDA
Instruments
FSP­
PFP­
5­
8,
Section
16.4
Calibration
Confirmation
for
Residues
Project
NDA
Instruments
E.
8
NDA­
SPECIFIC
REFERENCES
Hanford
TRU
Project
NDA
programs
were
developed
using
the
following
references:

E1
NUREG­
1297,
Peer
Review
for
High­
Level
Nuclear
Waste
Repositories,
Office
of
Nuclear
Material
Safety
and
Safeguards,
U.
S.
Nuclear
Regulatory
Commission,
Washington
D.
C.

E2
DOE­
CBFO­
94­
1012,
Quality
Assurance
Program
Document,
Carlsbad
Field
Office,
U.
S.
Department
of
Energy,
Carlsbad,
New
Mexico
E3
Currie,
Lloyd
A.,
1968,
"
Limits
for
Qualitative
Detection
and
Quantitative
Determination."
Anal.
Chem.
40:
586­
93
E4
EPA
520/
1­
80­
012,
Upgrading
Environmental
Radiation
Data,
Office
of
Radiation
Programs,
U.
S.
Environmental
Protection
Agency,
Washington
D.
C.,
1980
E5
"
Total
Measurement
Uncertainty
Assessment
for
Transuranic
Waste
Shipments
to
the
Waste
Isolation
Pilot
Plant,"
K.
C.
Smith,
R.
A.
Stroud,
K.
L.
Coop,
and
J.
F.
Bresson,
Proceedings
of
the
6th
Nondestructive
Assay
Waste
Characterization
Conference,
Salt
Lake
City,
Utah,
Nov.
17­
19,
1998,
pp.
21­
37
E6
"
Standardized
Total
Measurement
Uncertainty
Reporting
for
WIPP,"
K.
L.
Coop,
J.
F.
Bresson,
M.
E.
Doherty,
B.
M.
Gillespie,
and
D.
R.
Davidson,
Nondestructive
Assay
Interface
Working
Group,
Salt
Lake
City,
Utah,
May
22,
2000
E7
DOE/
CBFO­
01­
1006,
Performance
Demonstration
Program
Plan
for
Nondestructive
Assay
of
Boxed
Wastes
for
the
TRU
Waste
Characterization
Program,
Carlsbad
Field
Office,
U.
S.
Department
of
Energy
Carlsbad,
New
Mexico
HNF­
2600,
REV
15
Page
271
of
281
5/
11/
2005
HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
E8
ASTM
C1490,
"
Standard
Guide
for
Selection,
Training
and
Qualification
of
Nondestructive
Assay
(
NDA)
Personnel,
American
Society
for
Testing
and
Materials,"
Philadelphia,
Pennsylvania
E9
ANSI
N15.54,
"
Radiometric
Calorimeters
 
Measurement
Control
Program,"
American
National
Standards
Institute,
Inc.,
New
York,
NY
E10
DOE/
CBFO­
01­
1005,
Performance
Demonstration
Program
Plan
for
Nondestructive
Assay
of
Drummed
Wastes
for
the
TRU
Waste
Characterization
Program,
Carlsbad
Field
Office,
U.
S.
Department
of
Energy,
Carlsbad,
New
Mexico
E11
ASTM
C1030­
95,
"
Standard
Test
Method
for
Determination
of
Plutonium
Isotopic
Composition
by
Gamma­
Ray
Spectrometry,"
American
Society
for
Testing
and
Materials,
Philadelphia,
Pennsylvania
E12
ASTM
C1316­
95,
"
Standard
Test
Method
for
Nondestructive
Assay
of
Nuclear
Material
in
Scrap
and
Waste
by
Passive­
Active
Neutron
Counting
Using
a
252Cf
Shuffler,"
American
Society
for
Testing
and
Materials,
Philadelphia,
Pennsylvania
E13
ASTM
C1133­
96,
"
Standard
Test
Method
for
Nondestructive
Assay
of
Special
Nuclear
Material
in
Low
Density
Scrap
and
Waste
by
Segmented
Passive
Gamma­
Ray
Scanning,"
American
Society
for
Testing
and
Materials,
Philadelphia,
Pennsylvania.

E14
ASTM
C1458­
00,
"
Standard
Test
Method
for
Nondestructive
Assay
of
Plutonium,
Tritium
and
241
Am
by
Calorimetric
Assay,"
American
Society
for
Testing
and
Materials,
Philadelphia,
Pennsylvania.

E15
ANSI
N15.36­
1994,
"
Nondestructive
Assay
Measurement
Control
and
Assurance,"
American
National
Standards
Institute,
Inc.,
New
York,
NY
E16
Regulatory
Guide
5.11,
Nondestructive
Assay
of
Special
Nuclear
Material
Contained
in
Scrap
and
Waste,
Office
of
Nuclear
Regulatory
Research,
U.
S.
Nuclear
Regulatory
Commission,
Washington,
D.
C.

E17
ANSI
N15.22­
1987,
"
Plutonium­
Bearing
Solids
Calibration
Techniques
for
Calorimetric
Assay,"
American
National
Standards
Institute,
Inc.,
New
York,
NY
E18
Safety
Analysis
Report
for
the
TRUPACT­
II
Shipping
Package,
Westinghouse
Electric
Corporation,
Waste
Isolation
Division,
Carlsbad,
New
Mexico
E19
DOE/
EH­
0071,
Internal
Dose
Conversion
Factors
for
Calculation
of
Dose
to
the
Public,
U.
S.
Department
of
Energy,
July
1988
E20
DOE/
WIPP­
02­
3122,
Contact­
Handled
Transuranic
Waste
Acceptance
Criteria
for
the
Waste
Isolation
Pilot
Plant,
Carlsbad
Field
Office,
U.
S.
Department
of
Energy,
Carlsbad,
New
Mexico
HNF­
2600,
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15
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272
of
281
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HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
E21
HNF­
2599,
Hanford
Site
Transuranic
Waste
Characterization
Quality
Assurance
Project
Plan,
Hanford
TRU
Project
Office,
Richland
Operations
Office,
U.
S.
Department
of
Energy,
Richland,
Washington
E22
Hanford
TRU
Procedure:
WMP­
400,
Waste
Isolation
Pilot
Plant
(
WIPP)
Procedures,
Section
7.1.9,
"
Acceptable
Knowledge
Documentation
Management"

E23
Hanford
TRU
Procedure:
WMP­
400,
Section
1.2.1,
TRU
Training
and
Qualification
Plan
E24
Hanford
TRU
Procedure:
WMP­
400,
Section
1.2.2,
"
Qualification
of
NDA,
NDE,
Visual
Examination,
Transportation,
and
Inspection
and
Test
Personnel"

E25
Hanford
TRU
Procedure:
WMP­
400,
Section
6.1.1,
"
TRU
Software
Quality
Assurance"

E26
Hanford
TRU
Procedure:
WMP­
400,
section
7.1.6,
"
TRU
Waste
Project
Level
Data
Validation
and
Verification"

E27
Hanford
TRU
Procedure:
WMP­
400,
Section
1.3.2,
"
TRU
Nonconforming
Item
Reporting
and
Control"

E28
Hanford
TRU
Procedure:
WMP­
400,
Section
1.3.3,
"
TRU
Corrective
Action
Reporting
and
Control"

E29
Hanford
TRU
Procedure:
WMP­
400
Section
2.4.4,
"
TRU
Control
of
Measuring,
Testing
and
Data
Collection
Equipment"

E30
ASME
NQA­
2a­
1990,
Part
2.7,
"
Quality
Assurance
Requirements
for
Computer
Software
for
Nuclear
Facility
Applications,"
American
Society
of
Mechanical
Engineers,
New
York,
NY
E31
HNF­
11976,
Interval
Estimation
for
Statistical
Control
Limits
E32
HNF­
11977,
Performance
Control
Limits
for
Gamma
Assay
Systems
E33
ASTM
C1207­
03
"
Standard
Test
Methods
for
Nondestructive
Assay
of
Plutonium
in
Scrap
and
Waste
by
Passive
Neutron
Coincidence
Counting,"
American
Society
for
Testing
and
Materials,
Philadelphia,
Pennsylvania
HNF­
2600,
REV
15
Page
273
of
281
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11/
2005
HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
APPENDIX
F
HYDROGEN/
METHANE
SAMPLING
AND
ANALYSIS
HNF­
2600,
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274
of
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2005
HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
HYDROGEN/
METHANE
SAMPLING
AND
ANALYSIS
The
concentration
of
hydrogen/
methane
in
a
waste
container
can
be
used
to
determine
the
required
aspiration
time
prior
to
shipping
waste.
Sampling
personnel
will
collect
hydrogen/
methane
in
accordance
with
the
requirements
established
in
the
HNF­
2599,
Hanford
Site
Transuranic
Waste
Characterization
Quality
Assurance
Project
Plan,
Section
B1­
1.
The
analytical
method
used
is
based
on
ASTM
Method
D2650­
83,
using
a
gas
chromatograph
coupled
with
a
thermal
conductivity
detector
(
GC/
TCD).

The
required
quality
control
(
QC)
samples
associated
with
sampling
and
analysis
for
hydrogen/
methane
are
discussed
in
Section
F1.
The
information
obtained
from
the
hydrogen/
methane
analysis
is
used
for
meeting
DOT
requirements
during
shipment
of
containers,
as
described
in
Section
5.2.5.4
of
the
CH­
TRAMPAC.

The
hydrogen/
methane
data,
report
generation,
review,
and
validation
requirements
are
applicable,
and
those
requirements
are
discussed
in
Sections
F.
4
and
F.
5.

F.
0
WASTE
DRUM
SAMPLING
FOR
HYDROGEN/
METHANE
Data
Quality
Objectives
HSG
sampling
of
drums
is
described
in
HNF­
2599,
Section
B1­
1.
Sampling
for
hydrogen/
methane
can
occur
either
just
for
hydrogen/
methane
or
combined
with
sampling
for
HSG
analysis.

A
field
duplicate
sample
shall
be
sampled
for
each
sampling
batch.
The
result
comparison
from
the
drum
sample
and
the
field
duplicate
sample
assesses
the
precision
of
the
sampling
process.
The
analysis
of
a
field
blank
is
not
necessary.

Laboratory
completeness
will
be
expressed
as
the
number
of
samples
analyzed
with
valid
results
as
a
percent
of
the
total
number
of
samples
submitted
for
analysis.
Valid
results
are
defined
as
results
that
meet
the
data
usability
criteria
specified
in
Table
F­
1.

Table
F­
1
Hydrogen
Analysis
And
Quality
Assurance
Objectives
Compound
CAS
#
Precision
(%
RPD)
Accuracy
(%
R)
MDL
(
ppmv)
PRQL
(%
vol)
Complete
­
ness
(%)
Hydrogen
1333­
74­
0
<
25
70­
130
30
0.1
90
Methane
74­
82­
8
<
25
70­
130
30
0.1
90
1
%
vol
=
10,000ppmv
RPD
=
relative
percent
difference
%
R
=
Percent
recovery
MDL
=
method
detection
limit
PRQL
=
project
required
quantitation
limit
HNF­
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HANFORD
SITE
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WASTE
CERTIFICATION
PLAN
Table
F­
2
lists
the
field
QC
samples
and
the
frequency
of
taking
these
samples.

Table
F­
2
Summary
Of
Field
QC
Sample
Frequencies
QC
Sample
Direct
Canister
System
On­
Line
System
Equipment
Blank
Once
 
Completed
with
HSG
canister
certification
1
per
on­
line
batch
Field
Reference
Standard
Once
 
Completed
with
HSG
canister
certification
1
per
on­
line
batch
Field
duplicate
1
per
sampling
batch
1
per
on­
line
batch
Table
F­
3
provides
the
acceptance
criteria
for
the
field
QC
samples
and
corrective
actions
if
acceptance
criteria
are
not
met.

Table
F­
3
Summary
Of
Sampling
QC
Sample
Acceptance
Criteria
QC
Sample
Acceptance
Criteria
Corrective
Action
Equipment
Blank
Completed
during
HSG
Certification
N/
A
Field
Reference
Standard
Completed
during
HSG
Certification
N/
A
Field
duplicate
RPD
<
25%
for
detections
in
both
samples
>
PRQL
Nonconformance
if
RPD
>
25%
for
detections
in
both
samples
HNF­
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HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
F.
1
METHOD
REQUIREMENTS
The
analytical
method
in
LA­
523­
426,
"
Determination
of
Permanent
Gases
in
TRU
Waste
Container
Headspace,"
is
based
on
ASTM
Method
D2650­
83.
Analysis
is
performed
by
gas
chromatography
coupled
with
a
thermal
conductivity
detector
(
GC/
TCD).
The
minimum
requirements
of
quality
control
and
assurance
are
listed
in
Table
F­
4.
Table
F­
4
Laboratory
Quality
Control
Samples
and
Frequencies
For
Hydrogen
Analysis
QC
Sample
Minimum
Frequency
Acceptance
Criteria
Corrective
Action
Method
performance
samples
Seven
(
7)
samples
initially
and
a
minimum
four
(
4)
semiannually
Meet
method
QAOs;
70­
130%
R
for
concentrations
>
lowest
initial
calibration
standard
Repeat
until
acceptable
Field
Duplicates
One
(
1)
per
sampling
batch
RPD
<
25%
for
detections
in
both
samples
>
PRQL
Nonconformance
if
RPD
>
25%
for
detections
in
both
samples
Laboratory
blanks
One
(
1)
per
analytical
batch
Analyte
amounts
#
3
x
MDLs
from
Table
F­
1
Nonconformance
if
analyte
concentrations
>
3
x
MDLs
from
Table
F­
1
Laboratory
control
samples
(
LCS/
LCSD)
One
set
per
analytical
batch
70­
130
%
R;
RPD
 
25
for
LCS/
LCSD
Nonconformance
if
%
R
<
70
or
>
130
or
if
RDP
>
25
for
LCS/
LCSD
Technique
Procedure
Frequency
of
Procedure
Acceptance
Criteria
3­
pt
initial
calibration
Initially,
and
as
needed
%
RSD
of
response
factor
for
each
analyte
<
30;
correlation
coefficient
 
0.995
Initial
calibration
verification
(
ICV)
Immediately
following
3­
pt
calibration
70­
130
%
R
Continuing
calibration
verification
(
CCV)
Every
12
hours,
prior
to
laboratory
blank
and
every
12
hour
of
analysis
Peak
must
be
within
established
RT
window;
%
D
of
response
factor
 
25
compared
to
ACF
of
the
initial
calibration
GC/
TCD
Laboratory
blank
Every
12
hours,
after
CCV,
and
every
12
hours
of
analysis
Analyte
concentration
<
3
x
MDL
from
Table
F­
1
QAO
=
Quality
Assurance
Objective
%
R
=
percent
recovery
%
RPD
=
relative
percent
difference
RT
=
retention
time
%
D
=
percent
difference
MDL
=
method
detection
limit
GC/
TCD
=
gas
chromatograph/
thermal
conductivity
detector
HNF­
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TRANSURANIC
WASTE
CERTIFICATION
PLAN
F.
2
INSTRUMENT
TESTING,
INSPECTION
AND
MAINTENANCE
REQUIREMENTS
Analytical
personnel
test,
inspect,
and
maintain
analytical
equipment
to
ensure
that
the
QAOs
in
Table
F­
1
are
met.

F.
3
REPORT
GENERATION
Hydrogen/
Methane
Batch
Data
Report
The
Hydrogen/
Methane
batch
data
reports
will
be
generated
following
the
requirements
as
identified
in
WMP­
400,
Section
8.1.8,
"
Data
Management
for
Headspace
Gas
Sampling
and
Analytical
Results."

Hydrogen/
methane
batch
data
reports/
records
are
stored
in
accordance
with
WMP­
400,
Section
1.5.1,
"
TRU
Records
Management."

Hydrogen/
methane
results
are
reported
to
WWIS
in
accordance
with
WMP­
400,
Section
7.1.5.

F.
4
DATA
REVIEW,
VALIDATION
AND
VERIFICATION
Data
Generation
Level
Data
review
requirements
are
included
in
the
HNF­
2599,
Section
B3­
10,
for
verification
and
validation.

F.
5
CORRECTIVE
ACTION
The
corrective
action
process
is
outlined
in
the
HNF­
2599,
Section
B3­
13.

F.
6
RECORDS
The
hydrogen/
methane
analysis
generates
the
following
records,
which
shall
be
transmitted
to
the
SPO
in
accordance
with
procedure
WMP­
400,
Section
1.5.1:

 
Hydrogen/
Methane
Batch
Data
Report
F.
7
TRAINING
The
hydrogen/
methane
personnel
described
in
this
appendix
are
trained
in
accordance
with
WMP­
400,
Section
1.2.1,
"
TRU
Training
and
Qualification
Plan,"
and
WMP­
400,
Section
1.2.2,
"
Qualification
of
NDE,
NDA,
Visual
Examination,
Transportation,
and
Inspection
and
Test
Personnel".
HNF­
2600,
REV
15
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278
of
281
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11/
2005
HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
F.
8
PROCUREMENT
Procurement
of
hydrogen/
methane
equipment
will
be
performed
in
accordance
with
WMP­
400,
Section
2.3.1,
"
TRU
Procurement
Planning"
and
WMP­
400,
Section
2.3.2
"
TRU
Procurement
Document
Control."

F.
9
SOFTWARE
Software
associated
with
hydrogen/
methane
equipment
and
evacuation
is
controlled
by
WMP­
400,
Section
6.1.1,
"
TRU
Software
Quality
Assurance."
HNF­
2600,
REV
15
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279
of
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11/
2005
HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
F.
10
PROCEDURES
PERTINENT
TO
THIS
APPENDIX
Table
F­
5
lists
the
implementing
procedures
pertinent
to
hydrogen
sampling
and
analysis.

Table
F­
5
Hydrogen
Sampling
and
Analysis
Implementing
Procedures
Document
number
Title
TRU­
OP­
001
Headspace
Gas
Samples
of
TRU
Waste
Containers
LA­
523­
426
Determination
of
Permanent
Gases
in
Waste
Container
Headspace
Gas
Sampling
LO­
090­
450
Sample
Chain
of
Custody
Acceptance
and
Disposal
LO­
080­
407
Cleaning
SUMMA
 
Canisters
HNF­
2599
Hanford
Site
TRU
Waste
Characterization
Quality
Assurance
Project
Plan
WMP­
400,
Section
1.2.1
TRU
Training
and
Qualification
Plan
WMP­
400,
Section
1.2.2
Qualification
of
NDE,
NDA,
Visual
Examination,
Transportation,
and
Inspection
and
Test
Personnel
WMP­
400,
Section
1.3.1
TRU
Corrective
Action
Management
WMP­
400,
Section
1.3.2
TRU
Nonconforming
Item
Reporting
and
Control
WMP­
400,
Section
1.3.3
TRU
Corrective
Action
Reporting
and
Control
WMP­
400,
Section
1.5.1
TRU
Records
Management
WMP­
400,
Section
2.3.1
TRU
Procurement
Planning
WMP­
400,
Section
2.3.2
TRU
Procurement
Document
Control
WMP­
400,
Section
2.3.3
TRU
Control
of
Purchased
Items
and
Services
WMP­
400,
Section
6.1.1
TRU
Software
Quality
Assurance
WMP­
400,
Section
7.1.5
WIPP
Waste
Information
System
Data
Entry
and
Reporting
WMP­
400,
Section
7.1.7
TRU
Waste
Container
Management
Activities
WMP­
400,
Section
8.1.1
Logkeeping
Practices
for
Headspace
Gas
Sampling
and
Analysis
WMP­
400,
Section
8.1.8
Data
Management
for
Headspace
Gas
Sampling
and
Analysis
Results
HNF­
2600,
REV
15
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280
of
281
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11/
2005
HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
ABBREVIATIONS/
ACRONYMS
CBFO
Carlsbad
Field
Office
CH­
TRAMPAC
Contact
Handled
Transuranic
Waste
Authorized
Methods
for
Payload
Control
DOE
U.
S.
Department
of
Energy
DQO
Data
quality
objective
GGTP
Gas
Generation
Test
Program
(
the
Program)
ppm
parts
per
million
PRQL
Program­
required
quantitation
limit
QA
Quality
Assurance
QAO
Quality
Assurance
objective
QAPD
Quality
Assurance
Program
Document
QAPjP
Quality
Assurance
Project
Plan
QAPP
Quality
Assurance
Program
Plan
QC
Quality
Control
TRUPACT­
II
Transuranic
Package
Transporter­
II
VOC
Volatile
organic
compound
DEFINITIONS
Precision
is
a
measure
of
mutual
agreement
among
individual
measurements
of
the
same
property,
usually
under
prescribed
similar
conditions.

Accuracy
is
the
degree
of
agreement
between
a
measured
value
and
an
accepted
reference
or
true
value.

Representativeness
is
the
degree
to
which
sample
data
accurately
and
precisely
represent
a
characteristic
of
a
population,
parameter
variation
at
a
sampling
point,
or
an
environmental
condition.

Completeness
is
the
percentage
of
measurements
made
that
are
judged
to
be
valid
measurements.
The
completeness
goal
is
to
generate
a
sufficient
amount
of
valid
data
based
on
project
needs.

Comparability
is
the
degree
to
which
one
data
set
can
be
compared
to
another.
Sample
data
should
be
comparable
with
other
measurement
data
for
similar
samples
and
sample
conditions.
To
evaluate
comparability,
the
standards
shall
be
analyzed
to
the
same
degree
of
accuracy
and
precision.
HNF­
2600,
REV
15
Page
281
of
281
5/
11/
2005
HANFORD
SITE
TRANSURANIC
WASTE
CERTIFICATION
PLAN
APPENDIX
G
PAYLOAD
MANAGEMENT
OF
TRU
ALPHA
ACTIVITY
CONCENTRATION
(
The
Hanford
site
is
not
implementing
this
appendix
at
this
time.)
